ML20151Z698
| ML20151Z698 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 09/14/1998 |
| From: | IOWA STATE UNIV., AMES, IA |
| To: | |
| Shared Package | |
| ML20151Z691 | List: |
| References | |
| NUDOCS 9809220078 | |
| Download: ML20151Z698 (7) | |
Text
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3.0 LIMITING CONDITIONS FOR OPERATION (Continued) 3.7Rahation Monitorina Systems and Effluents 3.7.1 Applicability These specifications apply to the radiation monitoring systems and to the limits on effluent releases.
3.7.2 Objective To specify the minimum number of acceptable components or the lowest acceptable level of performance for the radiation monitoring systems and the limits for release of effluents.
3.7.3 Specifications The reactor shall not be made critical unless the following conditions exist:
A. The radiation monitoring channels and components shall be operable l in accordance with Table 3-3, including the minimum number of channels or components, and their setpoints.
3 B. The cumulative energy production of the reactor shall not exceed 4760 kilowatt-hours in any twelve-month interval nor exceed 100 kilowatt-hours in any 7-day interval to limit the generation and release of argon-41, C. If evidence exists that the limit in 3.3.3 G will be exceeded, the reactor i shall be shut down and the leakage source found and eliminated; however, the reactor may be operated intermittently to assist in determining the source ofleakage.
3.7.4 Bases i Specification A provides assurance that the required radiation monitors are operable.
m The air-particulate monitor is placed in service and operated continuously whenever designated experiments are being performed, 2
viz., those which could produce airborne radioactivity. The alarm
, setpoint is influenced by the normal background reading while the reactor operates at the required power level and is based on the same reasoning as given for the deionizer monitor setpoint.
5 (Paragraph deleted.)
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a The radiation area monitors are placed on the walls adiacent to the fuel storaae oit. (Sentence deleted.) The south and west units initiate an evacuation alarm at or above (phrase deleted) the radiation-evacuation setpoint gf 5 mR/h. The 5 mR/h limit is based on the minimum value l permitted for monitoring SNM in storage and applies when the area is unattended (phrase deleted).
m The doorway radiation monitor serves as a frisker to detect abnormal levels of radiation when a person passes the detector. The increasing aural signal alerts the reactor operator and the affected individual that 3 further assessment must be initiated.
l u The radiation film badge (or its equivalent) provides radiation dose information at the perimeter wall of the reactor room and serves as a
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control for the film badges used by personnel in the restricted area.
Specification B provides a conservative limit on the generation and release of argon-41 and is based on measurements at this facility (SAR: 4.5.4).
Argon-41 is the only significant radioactive effluent produced during normal operation of the reactor, and the limits provided meet the requirements of
- paragraphs 20.103 and 20.106 of 10 CFR Part 20. The first part of specification B is based on the assumption that the reactor operates continuously at 10 6 W for 476 hours0.00551 days <br />0.132 hours <br />7.87037e-4 weeks <br />1.81118e-4 months <br /> and that the dilution from diffusion of the air in the enclosure is only
- 10; for these conditions, the argon-41 concentration averaged over one year is about 50% of the value listed for unrestricted areas in Table 11, Appendix B of 10 CFR Part 20. The second part of specification B uses the assumption that the reactor operates continuously at 10 kW for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for one 40-hour week; these conditions yield an average concentration in the enclosure of 50% of the value listed for the restricted areas in Table I, Appendix B of 10 CFR Part 20.
Specification C allows a search for the leaking fuel assembly to be
, conducted by using the reactor to the extent needed to detect the source of fission products.
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l Table 3-3. Required Radiation Monitoring Channels or Components.
Channel Setpoint Min. Operable Function 1
Air-Particulate unit (a) As required 1 Alarm I
- - - - - - - - - - - - - - - -(Table Entry Deleted) - - - - - - - - - - - - - - - - - - -
Area units 5 mR/h 2 Alarm Doorway monitor --
1 Warn of abnormal ,
radiation level. I Environmental film -
1 Integrated dose in ,
restricted area.
l (a) This unit is activated whenever designated experiments are being performed.
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Technical Specification (Old) :
Section 3.7 Amendment # 12
3.0 LIMITING CONDITIONS FOR OPERATION (Continued)
$.7 Radiation Monitoring Systems and Emucpfs 3.7.1 Applicability These specifications apply to the radiation monitoring systems and to the limits on efiluent releases.
3.7.2 Objective To specify the minimum number of acceptable components or the lowest acceptable level of performance for the radiation monitoring systems and the limits for release of ellluents.
3.7.3 Specifications The reactor shall not be made critical unless the following conditions exist:
A. The radiation monitoring channels and components shall be operable in accordance with Table 3-3, including the minimum number of channels or components, and their setpoints.
B. The cumulative energy production of the reactor shall not exceed 4760 kilowatt-hours in any Iwelve-month interval nor exceed 100 kilowatt-hours in any 7 day inten al to limit the generation and release of argon-41.
C, If evidence exists that the limit in 3.3.3 G will be exceeded, the reactor shall be shut down and the leakage source found and eliminated; however, the reactor may be operated intermittently to assist in detennining the source ofleakage.
3.7.4 Bases Specification A provides assurance that the required radiation monitors are operable.
m The air-particulate monitcr is placed in senice and operated continuously wienever designated experiments are being performed, viz., those which could produce airborne radioactivity. The alarm setpoint is influenced by the normal background reading while the reactor operates at the required power level and is based on the same reasoning as given for the deionizer monitor setpoint.
m The radiation detector located near the deionizer initiates an alarm when the exposure rate exceeds five times the nominal value observed during normal full power operation. The trip value is sufficient for significant radiation events, yet not too sensitive to produce frequent false alarms. (See also 3.3.3. F.) This monitor would be the first to sense a release of fission products into the coolant.
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9, m The radiation area monitors are placed around the perimeter of the reactor room. All four
, , units are abic to initiate an alarm signal at or above 5 mR/h w henever the reactor console is
, energized. 'Ihc south and west units initiate an evacuation alarm at or above 50 mR/h when the reactor is in operation; wlen the console is not energized, the radiation-evacuation setpoint is 5 mR/h. The 5 mR/h limit is based on the minimunmlue permitted for monitoring SNM in storage and applies when the area is unattended, while the 50 mR/h limit is based on the radiation level associated with the emergency action level associated with the alert classification.
e The doorway radiation monitor serves as a frisker to detect abnormal levels of radiation when a person passes the detector. The increasing aural signal alerts the reactor operator and the affected individual that further assessment must be initiated.
m The radiation film badge (or its equivalent) provides radiation dose information at the perimeter wall of the reactor room and serves as a control for the film badges used by personnelin the restricted area.
Specification B provides a conservative limit on the generation and release of argon-41 and is based on measurements at this facility (SAR: 4.5.4). Argon-41 is the only significant radioactive effluent produced during normal operation of the reactor, and the limits provided meet the requirements of paragraphs 20.103 and 20.106 of 10 CFR Part 20. The first part of specification B is based on the assumption that the reactor operates continuously at 10 kW for 476 hours0.00551 days <br />0.132 hours <br />7.87037e-4 weeks <br />1.81118e-4 months <br /> and that the dilution from diffusion of the air in the enclosure is only 10; for these conditions, the argon-41 concentration averaged over one year is about 50% of the value listed for unrestricted areas in Table 11, Appendix B of 10 CFR Part
- 20. The second part of specification B uses the assumption that the reactor op..ates continuously at 10 kW for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for one 40-hour week; these conditions yicid an average concentration in the enclosure of 50%
of the value listed for the restricted areas in Table 1, Appendix B of 10 CFR Part 20.
Specification C allows a scarch for the leaking fuel assembly to be conducted by using the reactor to the extent needed to detect the source of fission products.
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Table 3-3. Required Radiation Monitoring Channels or Components.
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Cliannel Setpoint Min. Operable Function 1
Air-Particulate unit (a) As required 1 Alarm Deionizer unit (b) As required to 1 Alarm Satisfy 3.3.3 F Area units (c)(d) 5 (50)mR/h 4 Alarm Doorway monitor - 1 Warn of abnormal radiation level.
Emironmental film -
1 Integrated dose in restricted area.
(a) This unit is activated whenever designated experiments are being performed.
(b) 'Ihis unit serves as the fission product monitor specified in 3.3.3 F.
(c) When either the north or cast arca monitoring units are inoperable, portable instruments may be substituted for periods up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
l (d) The normal setpoint is shown. The parenthetical value is the maximum setpoint to be used depending on ;
local conditions. Use of higher than normal setpoints requires approval of the Reactor Manager. The j south and west units monitor the fuel storage area and are reset tot he normal value after shutdown.
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