ML20011A779
| ML20011A779 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/30/1981 |
| From: | Cross W FLORIDA POWER CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM 3F-1081-28, NUDOCS 8111030154 | |
| Download: ML20011A779 (8) | |
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- 3F-1081-28
'O Mr. Darrell G. Eisenhut, Director f
Division of Licensing 4
m Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 NUREG-0737 - Post-TMI Requirements item II.F.1 Additional Accident Monitoring Instrumentation
Dear Mr. Lisenhut:
Pursuant to Florida Power Corporation's letter (Baynard to Eisenhut) dated May 29, 1981, a submittal describing the final design details of the additional accident-monitoring instrumentation would im provided to you no later than October 30, 1981.
By letter (Baynard to Eisenhut) d<
d August 17, 1981, Florida Power Corporation transmitted the information relative to the noble gas effluent and iodine / particulate gaseous effluent monitors. As discussed with a member of your staff, the information relative to the containment pressure, water level, and hydrogen monitors will be submitted by January 1,1982, as originally requested by your letter dated October 31, 1980. The following information completes our actions relative to the documentation required on the containment high-range radiation monitors.
GENERAL INFORMATION/ DESCRIPTION The High-Range Gamma Radiation Monitoring System consists of four separate units, each (except the detector) capable of other uses but mrticularly suited in combination to constitute a highly reliable and versatile sy,teni wr detection of intense gamma radiation in a containment environment. The units are General Atomic's:
Model RD-23 Gamma Radiation Detector (gamma ionization chamber)
Model RP-2C Readout Module Model RP-23 Power Supply Oh Model RP-20-01 NIM Bin 811103015 DRADOCKohoghjj2
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-fourth Street South e P O Box 14042. St. Petersburg. Florida 33733 e 813-866 5151
3 Mr. Darrell G. Eisenhut
- 3F-1081-28 October 30, 1981 Page 2 Model RD-23 Gamma Radiation Detector The Gamma Radiation Detector, a gamma ionization chamber, detects radiation 0 o if Nbr with a uniform energy response (120%)in the range of 0.1 to from 10 t
3 MeV and sensitivr to 60 kev photons. As a safety monitor,it satisfies Class IE requirements and is qualified under LOCA conditions to IEEE 323-1974. The detector is encased in stainless steel to protect it from containment sprays and high temperatures. The detector locations are shown on Figure 1.
Model RP-2C Readout Module The Model RP-2C Readout Module accepts a signal current from the detector.
The module's log picoammeter operates upon the signal to generate a current analogous to the logarithm of the detector current. The log picoammeter output current is measured by an ammeter whose display is graduated in R/hr. Analog outputs for a front panel meter and a remote recorder are provided. Digital outputs in the form of relay contacts for alarm actuation are also provided.
The readout msdule also has two solid-state trip circuits that can be adjusted over the complete meter range. An additional feature is a self-checking failure trip that is actuated upon loss of power or high voltage or upon loss of signal from the detector.
Front panel controls include three alarm lights with reset pushbuttons and a sp-ing-loaded, three-position function switch for normal operations, trip level adjustments, and internal check signal actuation. In the CHECK position, an electric current is generated in the module to produce a midscale indication of 105 R/hr. Test points and adjustment potentiometers are accessible from the front panel. The test points and adjustments are recessed to prevent accidental adju:,. ment.
Model RP-23 Power Supnly The modular power supply for each readout module is mounted at the rear >f the NIM Bin. Input to the power supply is 115 V, 60 Hz. Its outputs to the n adout module are +24 dc. The power supply for each channel is from an in r;ndent vital source.
Model RP-20-01 NIM Bin This modified NIM Bin is capable of accepting six readout modules and their power supplies. However, only two units are utilized with distances and a physical barrier provided for channel separation.
2
4 Mr. Darrell G. Eisenhut
- 3F-1081-28
- October 30,1981 Page 3 SPECIFICATIONS
' Model RD-23 Gamma Radiation Detector
' TABLil 1-1 MODEL RD-23 GAMMA RADIATION DETECTOR SPECIFICATIONS Gamma ionization charnber with internal radiation source providing a self-test signal corresponding to approximately IR/hr.
Parameter Description 0 o 108 R/Hr Range 10 t
Sensitivity approx. I x 10-11 Amp / Rad /Hr i
Max Temp 3500F (1770C)
Max Pressure 70 lb/in 2 (4.9 kg/cm 2) gauge Humidity 0% - 100% (saturated steam)
Weight (approx.)
9.5 lbs (4.3 kg)
Seismic Tested per IEEE-344-1975 using random biaxial inputs.
3 m
-m m
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Mr. Darrell G. Eisenhut
- 3F-1081-28 October 30,1981 Page 4 Model RP-2C Readout Module TABLE 1-1 MODEL RP-2C READOUT MODULE SPECIFICATIONS Parameter Description Model number RP-2C 8
Range 100 to 10 R/Hr 1
Dimensions 2X NIM standard module Weight 3.8 lb (1.75 kg)
Connector 42-pin NIM type Operational environ-ment Temperature 40 to 560C (39o to 131oF)
Humidity Up to 95% (without condensation)
Accuracy -
+3% of the linear full scale equivalent at normal control room temperatures Temperature drift 40.1% of full scale /oC Time constant (RC)
(25 msec (10-11 A to 10-3 A)
Seismic Up to 2 g over a 0.5-to 50-Hz bandwidth Alarms TRIP 1: Adjustable over full scale; can be wired on trip-on-increasing or -decreasing signal or for latching or nonlatching (manual or automatic reset) operation; amber light; two DPDT (form C) relay contacts rated at 2 A at 50 V de or 0.5 A at 120 V ac; logic outputs of O or
+12 V dc (output 1) and +12 or 0 V dc (output 2)
TRIP 2: Same as TRIP 1 except red light 4
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O Mr. Darrell G. Eisenhut
- 3F-1081-28 October 30,1981 Page 5 TABLE l-2 (continued)
Parameter Description Failure: Relays open and close, green OPERATE light off( normally on)
Analog outputs Recorder 0.000 to 1.000 V, short-circuit-protected Data logger or 0.000 to 0.100 V, short-circuit-protected c omputer Remote meters Two,0.0 to 1.0 mA and 0.0 to 100.0p A, short-circuit-protected Front panel 2.4-in.-scale, vertically mounted meter; spring-loaded function switch: cw rotation to the TRIP AD3 position energizes the trip reference circuitry, and ccw rotation to the CHECK position transmits a check-current signal to the log picoammeter; each alarm light incorporates a trip-reset pushbutton; test points and adjustments are front-panel accessible High voltage Normally fixed at 875 V dc; can be field-adjusted for voltages from 500 to 900 V de Power supply Normally, General Atomic Mode RP-23 (see Table 1-3);
1 5 V de, 35 mA, 1
1 5 V de,550 mA, max;-24.0
+ 24.0 1
max 5
.Mr. Darrell G. Eisenhut
- 3F-1081-28 October 30,1981 Page 6 Model RP-23 Power Supply TABLE l-3 MODEL RP-23 POWER SUPPLY SPECIFICATIONS Parameter Description Dimensions 2.7 in. (7 cm) wide,5.3 In. (13.5 cm) high, and 5.9 in.
(15 cm) deep Input 120 V 110%, 60 Hz 110 %
1 5 V de,1.2 A max, g20 mV rms ripple; Output 124.0 1
1 5 V de,0.5 A max,310 mV rms ripple
-24.0 1
Features Input lines both fused, overload-and short-circuit-protected Weight 3.3 lbs Model RP-20-01 NIM Bin TABLE 1-4 MODEL RP-20-01 NIM BIN SPECIFICATIONS Parameter Description Capacity Maximum of six area monitor modules (RP-2A or RP-2C) or four radiation analyzer modules (RP-30A) and power supplies Dimensions 19 in. (48.3 cm) wide, 8-3/4 in. (22.2 cm) high, and 10-K in. (26.7 cm) deep Weight 20.2 lbs 1
6
Mr. Darrell G. Eisenhut 13F-1081-28
_ October 30,1981 Page 7 CALIBRATION All monitors are factory calibrated; additionally, each monitor will be calibrated in place with a calibrated radiation source. In addition, calibration of each RP-2C readout -
module to the sensitivity of the detector to which it is mated and verification of system linearity throughout its range is accomplished electronically.
This monitoring system is scheduled to be operable by January 1,1982.
Very truly yours, h A$l k-William A. Cross Manager Nuclear Licensing Attachment 7
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