ML20117A800

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Forwards Info Which Constitutes Second Annual Rept Required by Rev One to TS
ML20117A800
Person / Time
Site: Rhode Island Atomic Energy Commission
Issue date: 08/20/1996
From: Tehan T
RHODE ISLAND, STATE OF
To: Mendonca M
NRC (Affiliation Not Assigned)
References
NUDOCS 9608260286
Download: ML20117A800 (8)


Text

TA,TE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS RHODE ISLAND ATOMIC ENERGY COMMISSION j

Nudear Science Center 1

South Ferry Road j

Narragansett, R.I. 02882-1197 August 20, 1996 Docket No. 50-193 i

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, DC 20555 s

Dear Mr. Mendonca:

This letter and enclosures constitute the second annual report that is required by revision one to the Technical Specifications. Enclosure 1 provides reactor operating statistics.. Enclosure 2 provides information on the 1 emergency shutdown. discusses maintenance operations. Enclosure 4 describes changes to the facility and enclosure 5 provides radiological controls information.

If there ' are any questions regarding this information, please call me at 401-789-9391.

1 Sincerely,

-Q ol Terry han Dir r

TT:cd Enclosures (5)

I Copy to:

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9608260286 960820 PDR ADOCK 05000193 P

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Technical Specifications Section 6 8.4.a.

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i Reactor Energy Energy Critical Generated Generated Month (hours)

(MWh)

(mwd)

July-95 87.15 148.49-6.19 August-95 102.77 168.30 7.01 September-95 66.97-117.17 4.88 October-95 126.75 212.39 8.85 I

November-95 19.63 31.41 1.31 December-95 0.00 0.00 0.00 I

January-96 0.00 0.00 0.00

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February-96 0.00 0.00 0.00 March-96 11.60 0.87 0.04 j

April-96 50.75 5.08 0.21 May-96 84.98 8.5d 0.35 June-96 63.38 6.34 0.26

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l 1995-96 Totals:

613.98 698.55 29.11 Total Energy Output since Initial Criticality:

54,580.02 2,274.17 1

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-~+e a-m Technical Specifications Section 6.8.4.b.

INADVERTENT EMERGENCY SHUTDOWNS AND SCRAMS i

Date Run No.

Book / Pace Remarks Reason 8/31/95 6840 45/14 Dropped Blade 4 Drive misalignment l

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Section 6.8.4.c.

Maintenance Operations 1995-96 The reactor is normally operated daily (one shift) at its maximum licensed power level of 2MWt in support of the NAA i

and Neutron Scattering research conducted at the facility.

The reactor has been operating at a reduced power level of 100KWt while the reactor cooling systems are isolated and drained for an upgrade. Including the installation of two new primary pumps and the installation of an additional secondary cooling system.

Primarv/Secondarv Uoorade The new components will become a redundant system insuring forced convection cooling capability. System flow rates have been increased providing for better coolant safety margins.

j This. upgrade is in preparation for a fut.ure operating license change with a maximum power level limit of SMWe.

Emercency Core Coolina System The ECCS is 4.nstalled. It provides a redundant path to automatically maintain the pool water at near full level.

This system insures against a loss of coolant accident, i

Pool leak l

The reactor pool leak, being temperature dependent, has slowly decreased from 25 gallons per day to 8 gallons per day while the reactor has been operated at 100KWe for the past 8 months. The leak water is first noticed on the main reactor floor below the bottom of the thermal column housing, indicating the probable leak being a failure in the welded joint of the thermal column to pool liner. Inspections to pinpoint the location of the leak in the welded joint from the pool side is obstructed by the rabbit, beam port and i

thermal column protrusions into the pool. Fixing this leak is the top priority for funding requests under the Department of Energy Grant Program.

A grove was cut in the concrete floor at the thermal column to direct the water to a drain reducing the wetted floor area in front of the thermal column. The leak water then drains through a hole in the main floor to a 500 gallon tank located in the reactor basement area. From the tank the leak water is pumped through a 10 and 1 micron filter media to the suction of the reactor pool water demineralizer system and back to the pool.

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Radioactive liauid effluents l

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As part of a waste water management plan to reduce the amount of water being discharged from the facility, the pool leak 1

water is now filtered and pumped back into the primary water demineralizer system and returned to the pool.

j In addition, the pool water level was lowered approximately 2 inches (within Technical Specifications) to minimize the l

possibility of normal pool water temperature changes causing a pool water discharge to the retention tanks.

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Both underground retention tanks, (15,000 gals and 1,000 gals), are no longer in service. Both tanks are over 30 years old and have become degraded. It was decided to abandon them in place. The tanks were emptied. The manifolds have been removed and the piping capped off. Personnel access points have been sealed and locked. All radioactive liquids now drain into plactic tanks (900 gallon capacity) installed inside the facility basement.

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The following are descriptions of 10 CFR 50.59 evaluations conducted during the period covered by-this report in accordance with Technical Specifications, section 6. 8. 4. d.

The evaluations did not find any new types of failures that would result in effects not previously considered in the FSAR:

1. 5-15-95, Primary and Secondary systems upgrade.

This upgrade is in anticipation of a licensed reactor power level increase to 5 megawatts.

The upgrade consists of replacement of the original primary pump (1500 gpm) with one having higher flow capacity (2000 gpm), and adding an additional primary / secondary system with - the same capacities to provide the necessary cooling for operation at 5 megawatts. In the interim this change provides a redundant system for reactor operation at 2 megawatts.

2. 1-30-96, Replacement of the containment system air compressor.

The original air compressor failed and resulted in an air system reziew. Air pressure is used to operate (open and close) ~ the containment isolation valves (reactor building air supply and exhaust). These valves are used in conjunction with a ventilation blower to provide a negative pressure in the reactor building.

The replacement air compressor has - twice the air tank capacity and a higher air flow providing for increased reliability. All the air lines were replaced using larger size piping which improved the operating characteristics of the isolation valves.

The new equipment does not create an unresolved safety question.

3. 3-14-96, Adding a window to the inside reactor room entry door.

l The security type glass window provides both security

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and safety enhancements for personnel using the reactor room doorway by being able to view condtions on the-opposite side of the door prior to opening it. This change does not interfere with containment. A glass break would have a similar effect as a gasket failure an j

therefore does not create an unresolved safety question.

4. 5-15-96, Install a leak recovery system.

A small pump.and filter system has been installed to recover the pool leak water (approx. 10 gallons per day) 4 e

A (continued) and pump it back to the primary water demineralizer system. The recovery system consists of a metering pump and two filters ( 10 micron and 1 micron) and a float switch.

The leak water, which is of lower conductivity than tap

water, is collected in a

500 gallon tank.

Upon activation by a high water level switch the tank water is pumped through the two filters and into the suction line of the demineralizer system pump and then to the demineralizer resin tank prior to being sent back to the pool. A check valve is installed in the line to the demineralizer system to prevent a line break from causing a pool leak which would drain the pool to the anti-siphen lines as described in the FSAR.

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1 RINSC ANNUAL REPORT ll:)

JULY 1, 1995 - JUNE 30, 1996 TECHNICAL SPECIFICATIONS SECTION 6.8.4 l

4e.

Environmental surveys performed outside the facility.

A quarterly TLD badge is deployed outside the northeast wall of the reactor building where large radioactive equipment is stored.

The doses are given below.

This is an area which is not frequented by the general public. Using an occupancy factor of 1% (0.01) the annual dose will be belov 50 mrem.

i OUARTER DQg 08/01/95-09/30/95 200 mrem 10/01/95-12/31/95 200 mrem 01/01/96-03/31/96 330 mrem 04/01/96-06/30/96 Not Received Yet 4f.

Annual radiation exposures in excess of 500 mrem.

There were no exposures above this limit.

49 Radioactive Effluents C.f L ? ': ? 5 1.

Gaseous ef fluent -concentrations are documented on the Monthly Information Sheets (Form NSC-78 enclosed).

The gaseous effluents, mainly Argon-41, are about 3-4% of the maximum permissible concentrations.

2.

Liquid effluents concentrations, released to the sewer, are documented on the sewer disposal record (Form NSC-32).

The concentrations were well below the monthly sewer limits.

A summary sheet is attached.

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