ML16319A300
| ML16319A300 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 11/14/2016 |
| From: | Goodwin C State of RI, Rhode Island Nuclear Science Center |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16319A298 | List: |
| References | |
| Download: ML16319A300 (15) | |
Text
3.2 METEOROLOGICAL DAMAGE Tornadoes are rare in Rhode Island. Based on the small probability of occurrence, postulated low intensity, the intermittent type of reactor operation and low fission-product inventory, no criteria for tornadoes have been established for the RINSC structure. The RINSC reactor core is protected from damage by high winds or tornadoes by virtue of its location in the thick reinforced concrete structure surrounding the reactor tank. The superstructure of the RINSC has been designed for area wind loads including those associated with the infrequent hurricanes reaching the Rhode Island coast. The reactor building has survived past hurricanes with only light damage to the facility roof in 1991. There was no damage to the facility from the most recent hurricanes in the area: Hurricane Irene (2011) and Hurricane Sandy (2012). -
Facility design also accounts for snowstorms and severe cold weather, which has not presented significant problems in the past.
3.3 WATER DAMAGE As discussed in Chapter 2, flooding is not expected at the RINSC site. The lowest elevation at the facility is 97.0 Feet above sea level and the facility is located 550 feet from the Narragansett Bay. However, even if flooding occurred, reactor safety would not be an issue since the core is located in a water pool. In the event of a severe storm or flood, the reactor will be shut down if there appears to be even a remote chance of danger in operating the reactor at the time.
4.2.2 Control Rods The facility has an analog rod drive system that has a digital indication of rod position. The digital system can be used to drive the analog system. The digital system is in series with the analog system.
4.3 Reactor Pool - info regarding pool leaks Each of the beamports and the through tube have a 1/2 drain line associated with them for the detection of leaks. These lines come together and are collected in the basement near the make-up system and ion exchanger. This is checked daily for signs of leakage from these experimental facilities.
As part of securing the facility each day, the change in the running total volume of make-up water that has been added to the pool is recorded on RINSC Form NSC - 15 RINSC Checklist for Securing Reactor Facility. If the volume has changed by more than 100 gallons over a three day period, notify the Radiation Safety Officer. The RSO and Health Physicist shall investigate and determine the cause.
4.3.1 Reactor Pool Dam:
The reactor pool is separated into three different sections:
- High Power (HP) Section
- Middle Section
- Low Power (LP) Section 1
When the reactor is located in the HP Section it is coupled with the reactor forced convection cooling system and is capable of operating at full power. The reactor can be placed in the LP Section of the pool for operation adjacent to the Dry Irradiation Facility (DIF). In the LP Section the reactor is limited to a maximum power level of 100kW using natural convection cooling. The reactor will not be operated in the middle section. The reactor will not be operated with the dam in place.
The dam is normally stored on the north side of the middle section. The dam can be placed on either the east or west sides of the middle section, facing the LP or HP Sections, respectively.
The HP or LP Sections can be isolated for maintenance, repairs, or leak mitigation. Once the dam is in place the appropriate section can be drained IAW facility procedures.
The dam is 52 inches wide and 32 feet tall. There is a frame around it that is 4.5 inches thick and a rubber gasket on one side of the frame. For installation the aluminum cat walk is first removed from the pool. A guide rope is then installed on each side of the bridge and the crane hook is attached to the cable located on the top of the dam. The dam shall be positioned so that the side with the gasket is facing the side to be drained. The dam is then lowered onto the damming hooks (see image below).
Below is an image of the dam installed in the low power section of the pool.
Damming Pipe Hooks Protrusions 2
5.7 AUXILIARY SYSTEMS USING PRIMARY COOLANT There are no auxiliary systems that use primary coolant directly, however the Auxiliary Water Supply is related to the Primary Cooling System because it serves as an independent means of adding water to the primary loop in an emergency.
5.7.1 Auxiliary Water Supply System The Auxiliary Water Supply System provides an independent source of water for adding water to the pool in the event of a loss of coolant accident. Water is supplied from the fire sprinkler system supply, through a series of manual valves, up to the top of the pool. Since the water from this system does not go through a clean-up system, it is for emergency use only, and can only be turned on manually. The pipe entering the pool has a diameter of 1.25 inches.
Supplemental info: The flow rate of this system is approximately 60 gpm.
Emergency Generator Loads Load Run Amps Full Load Starting Amps Evacuation System 0.4 0.4 Generator Water Heater 0.2 0.2 Emergency Lighting 4.2 4.2 Emergency Exhaust Blower 3.5 8.9 Sump Pump 8.0 8.0 Dilution Air Blower 16.0 18.4 Stack Monitor Receptacle 5.6 5.6 Total Amps 37.9 45.7 Emergency Generator Operation Time
- 1. We have:
Onan Electric Generator Model 15 RJC-4RB/3745A Serial Number 3YC7759092
- 2. It is rated for:
15 kW 18.75 kVA 120/208 3 Phase 4 Wire 60 Cycle AC
- 3. Fuel Consumption Calculation:
3
The attached table shows that the RINSC generator uses approximately 110 ft3 of propane vapor per hour of operation at full load.
According to the table, the conversion between one gallon of liquid propane, and cubic feet of propane vapor is:
1
[ ]
36.5 3 Therefore the rate at which liquid propane is used during operation at full load is:
1 110 3
[ ][ ]
36.5 3 3.01
= [ ]
We have two propane tanks that each have the capacity for 100 gallons of liquid propane, so the maximum amount of time that the generator could operate under full load is:
2 100
[ ][ ][ ]
1 3
= 66.67
- 4. Therefore, if the tanks are kept at least half full, there will be enough fuel to run approximately 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, during which we could re-fuel if necessary.
4
100 AMP ONAN WESTERBEKE ENGINE CIRCUIT GENERATOR BREAKER SPECIFICATIONS SPECIFICATIONS
- 1. Inline 4 cylinder 1. 120/208 V LINE TRANSFER
- 2. Water cooled 2. 3 phase SWITCH
- 3. 850 W water heater 3. 15 kW/18.75 kVA 120/208 V
- 4. 1800 rpm 4. 60 Hz/52.6 amps 60 AMP
- 5. Propane gas fuel 5. 0.8 power factor 3 PHASE
- 6. 1800 rpm SPECIFICATIONS
- 1. Generator starts at 70% of normal voltage
- 2. Loads switch back GENERATOR CIRCUIT PANEL to normal supply at 90% of normal voltage
- 1. Evacuation System (TS Req)
- 3. Trickle charge of
- 2. Generator Water Heater generator battery
- 4. Emergency Exhaust Blower (TS Req)
- 5. Sump Pump
- 6. Dilution Air Blower (TS Req)
- 7. Stack Monitor Receptacle
Assumptions
- 1. Hot channel factors included
- 2. Inlet temperature is 115° F, maximum possible
- 3. Water depth is 23.54 feet above active core, minimum allowed Flow Instability Critical Heat Flux - Sudo & Kaminaga (Some of the experimental data used to develop the correlation did not distinguish between CHF and flow instability.)
Onset of Nucleate Boiling LSSS with Measurement Uncertainties Nominal Operating Point Safety Limit LSSS Figure 4.6 Reactor Powers at Which Onset of Nucleate Boiling, Critical Heat Flux, and Flow Instability are Predicted to Occur
2016 COMPLY REPORT COMPLY: V1.6. 8/24/2016 2:32 40 CFR Part 61 National Emission Standards for Hazardous Air Pollutants REPORT ON COMPLIANCE WITH THE CLEAN AIR ACT LIMITS FOR RADIONUCLIDE EMISSIONS FROM THE COMPLY CODE - V1.6.
Prepared by:
RI Atomic Energy Commission RI Nuclear Science Center 16 Reactor Rd.) Narragansett) RI 02882 C. Hathaway 401-874-2600 Prepared for:
U.S. Environmental Protection Agency Office of Radiation and Indoor Air Washington) DC 20460 Page 1
2016 COMPLY REPORT COMPLY: V1.6. 8/24/2016 2:32 2016 RINSC Argon Calculations SCREENING LEVEL 4 DATA ENTERED:
Release Rate Nuclide (curies/YEAR)
AR-41 5.491E+01 Release height 35 meters.
Building height 15 meters.
The source and receptor are not on the same building.
Building width 18 meters.
Building length 20 meters.
STACK DISTANCES) FILE: Stack Data 2016 Distance DIR (meters)
N 100.0 NNE 100.0 NE 100.0 ENE 100.0 E 100.0 ESE 100.0 SE 100.0 Page 2
2016 COMPLY REPORT SSE 100.0 S 100.0 SSW 100.0 SW 100.0 WSW 100.0 W 100.0 WNW 100.0 NW 100.0 NNW 100.0 COMPLY: V1. 6. 8/24/2016 2:32 WINDROSE DATA) FILE: 2016 WINDROSE DATA Source of wind rose data: FSAR Dates of coverage: 1954-1994 Wind rose location: Narragansett) RI Distance to facility: 155m Percent calm: 0.05 Wind Speed FROM Frequency (meters/s)
N 0.062 2.00 NNE 0.058 2.00 NE 0.044 2.00 ENE 0.013 2.00 E 0.012 2.00 ESE 0.013 2.00 SE 0.058 2.00 SSE 0.049 2.00 S 0.058 2.00 SSW 0.084 2.00 SW 0.105 2.00 WSW 0.064 2.00 W 0.068 2.00 WNW 0.095 2.00 NW 0.104 2.00 NNW 0.068 2.00 He produces his own VEGETABLES at home.
He produces his own MILK at home.
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2016 COMPLY REPORT He produces his own MEAT at home.
NOTES:
The receptor exposed to the highest concentration is located 100. meters from the source in the NE sector.
He produces his own VEGETABLES at his home.
He produces his own MEAT at his home.
He produces his own MILK at his home.
Input parameters outside the llnormal ll range:
Wind rose wind frequency is unusually LOW.
/tI COMPLY: Vl.6. 8/24/2016 2:32 RESULTS:
Effective dose equivalent: 1. 2 mrem/yr.
- Comply at level 4.
This facility is in COMPLIANCE.
It mayor may not be EXEMPT from reporting to the EPA.
You may contact your regional EPA office for more information.
- END OF COMPLIANCE REPORT **********
Page 4
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- GAM M A S P E C T RUM A N A L Y SIS *****
F{ name: HPGE Report Generated On 7/7/2016 4:06:17 PM Sample Title Matt Primary Sample 7/7/16 Sample Description 7/7/16 Sample Identification Sample Type Sample Geometry Peak Locate Threshold 3.00 Peak Locate Range (in channels) 1 - 65535 Peak Area Range (in channels) 1 - 65535 Identification Energy Tolerance 1. 000 keV Sample Size 9.800E+000 mg Sample Taken On Acquisition Started 7/7/2016 3:32:12 PM Live Time 1800.0 seconds Real Time 1805.9 seconds Dead Time 0.32 %
Energy Calibration Used Done On 7/7/2016 Efficiency Calibration Used Done On 9/3/2015 Efficiency ID 500mL Mar H20
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Peak Analysis Report 7/7/2016 4:06:17 PM Page '2
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Detector Name: HPGE Sample
Title:
Matt Primary Sample 7/7/16 Peak Analysis Performed on: 7/7/2016 4:06:17 PM Peak Analysis From Channel: 1 Peak Analysis To Channel: 4096 Peak ROJ ROJ Peak Energy FWHM Net Peak Net Area Continuum No. start end centroid (keV) (keV) Area Uncert. Counts 1 613- 622 617.15 352.05 1. 28 7.20E+001 12.31 3.50E+001.
2 1136- 1145 1140.82 609.25 1. 55 6.42E+001 10.86 2.38E+001 3 2869- 2880 2873.96 1460.66 1. 49 6.50E+001 8.52 3.00E+000 M First peak in a multiplet region m Other peak in a multiplet region F Fitted singlet Errors quoted at 1.000 sigma
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Interference Corrected Activity Report 7/7/2016 4:06:17 PM Page 3
- N U C LID E IDE N T I F I CAT ION REP 0 R T *****
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Sample
Title:
Matt Primary Sample 7/7/16 Nuclide Library Used: C:\GENIE2K\CAMFILES\STDLIB.NLB IDENTIFIED NUCLIDES Nuclide Id Energy Yield Activity Activity Name Confidence (keV) (% ) (uCi/mg ) Uncertainty K-40 0.996 1460.81* 10.67 1.03365E-004 1.38318E-005 BI-211 0.515 351.10* 12.20 2.86889E-005 4.94318E-006 404.80 4.10 BI-214 0.337 609.31* 46.30 1.11065E-005 1. 89332E-006 768.36 5.04 1120.29 17.00 1238.11 5.94 1764.49 17.00
- = Energy line found in the spectrum.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance: 1.000 keV Nuclide confidence index threshold 0.30 Errors quoted at 1.000 sigma
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Interference Corrected Activity Report 7/7/2016 4:06:17 PM Page "4
- I N T E R FER ENe E COR R E C TED REP 0 R T *****
Nuclide Wt mean Wt mean Nuclide Id Activity Activity Name Confidence (uCi/mg ) Uncertainty K-40 0.996 1.033647E-004 1.383183E-005 BI-211 0.515 2.868888E-005 4.943177E-006 BI-214 0.337 1.110652E-005 1.893324E-006
? nuclide is part of an undetermined solution X nuclide rejected by the interference analysis
@ nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000 sigma
- U N IDE N T I FIE D PEA K S **********
Peak Locate Performed on: 7/7/2016 4:06:17 PM Peak Locate From Channel: 1 Peak Locate To Channel: 4096 Peak Energy Peak Size in Peak CPS Peak Tol. (
No. (keV) Counts per Second % Uncertainty Type Nuclide All peaks were identified.
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