ML20039B250
| ML20039B250 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 12/15/1981 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20039B245 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8112220459 | |
| Download: ML20039B250 (5) | |
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PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES Big Rock Point Plant oc1281-0014a142 8112220459 811215 PDR ADOCK 05000155 PDR P
61 6.4.1 Process Radiation Monitoring System (Contd)
(b) Stack Gas Monitoring System There shall be an isokinetic probe, permanently fixed in the stack approximately one-third up from the base, to collect stack gas and particulate samples that are. withdrawn with a gas pump through flowmetering and regulating equipment. The monitoring system will be divided into a high range (accident) monitor consisting of a removable particulate and iodine filter and an ion chamber for noble gas monitoring and a normal range monitor consisting of a gamma scintillation detector monitoring the, removal particulate-and iodine filters and downstream of this a beta scintillation detector for noble gas monitoring. The gas flow is automatically switched from the normal to the high range monitor for high activity samples. The filters for the normal range monitor shall be removed and checked for radioactive contamination as specified in Section 6.4.3(b).
The equipment shall permit determination _gf fissign gas activities and gaseous activation products from 10 to 10 uCi/cc. The system shall have a high radiation alarm which shall be annunciated in the control room.
The alarm setting is specified in-Section 6.4.3(b).
(c) Emergency Condenser Vent Monitor The emergency condenser vent shall be monitored to detect a significant release of radioactive material. Monitoring shall be supplied by two independent gamma sensitive instrumentation channels employing scintillation crystal sensing devices. These channels shall have a range of 0.1 to 100 mr/hr and shall be provided with an alarm which shall annuniciate in, the control room to inform the operator or a release of radioactive material. The alarms shall be specified in 6.4.3(c).
(d) Process Liquid Monitor System A process liquid monitor system employing gamma scintillation detector channels shall be provided to give indication of radioactivity trends in process liquid streams normally containing radioactive liquids and also to warn the operator of radioactivity in process liquid streams that do not normally contain radioactive liquids. Alarms on monitors (i), (iv) and (v) shall be see so as to warn the control room operator via a common annunciator when concentrations are'present which exceed those listed in Column II, Table II, Appendix B of 10 CFR 20.
The remaining alarms shall also annunicate on this common annunciator and shall be set to alert the operator to unexpected changes in radioactivity levels.
These setpoints will be based on experience. The process liquid streams which shall be monitored are as follows:
(i)
Radioactive Waste System Effluent to Canal (ii)
Reactor Enclosure Cooling Water (iii) Main Condensate Demineralizer Influent.
(iv)
Circulating Water Discharge (v)
Service Water Return From Reactor Enclosure nu1281-0014bl42 Proposed
63 6.4.2 (Contd)
(c) At least five environmental film or TLD monitoring stations shall be provided for determining the integrated gamma dose rate in the site environs. These stations shall be placed on an arc of about 1,350 meters from the stack.
(d) Four narrow range water level monitors are provided in the main control room as part of the Reactor Detpressurizing System to be used for detection of adequate core cooling during accident situations.
6.4.3 Operating Requirements (a) At least one of the two air ejector off gas monitoring systems shall be in service during power operation and set to initiate closure of the off gas isolation valve as described below. Ala rms normally shall be set to annunciate in the control room if the off gas radioactivity reaches a level that corresponds to a stack release of 0.1 curie per second. At stack releases above 0.1 curie per second, the alarm shall be set approximately a factor of two above the expected off gas release rate but in no event above that level corresponding to a stack release of 0.47/E curie per second where E is the average gamma energy per disintegration (MEV/ dis).
If the limit of 0.47/E curie per second is exceeded, reactor power shall be immediately reduced such as to meet the limits. The monitors shall be set to initiate closure of the off-gas isolation valve (after a time adjustable from 0 to 15 minutes) if the off gas radioactivity reaches a level that would correspond to a stack release rate of ten curies per second. Off gas samples shall be taken monthly during power operation and analyzed for calibration of the off gas radiation monitors. The automatic closure function of the monitors shall be tested monthly during power operation.
(b) The stack gas monitoring system shall normally be in service.
With the monitoring system inoperable, restore to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or, in lieu of any other report required by Speci-fication 6.9.2, prepare and submit a Special Report to the Cemmission pursuant to Specification 6.9.4 within the next 14 days outlining the cause of the inoperability and the plans for restor-ing the system to OPERABLE status.
The alarm normally shall be set to annunicate in the control room at a level that corresponds to a stack release rate of 0.1 curie per second. At stack release rates above 0.1 curie per second, the alarm shall be set approxi-mately a factor of two above the expected stack release rate, but in no event above 0.47/E curies per second.
The calibration of the normal and high range monitoring system shall be checked at least monthly. The particulate and iodine filters of the normal range monitor shall be analyzed at least weekly.
(The filters of the high-range monitor are not used during normal operation.
(c) One of the emergency condenser vent monitors shall be in service at all times during power operation. The monitors shall be set to nul081-0017c142 Proposed
64 6.4.3 (Contd) alarm at approximately 10 mr above the maximum expected background during operation of the emergency condenser. The calibration shall be checked at least monthly.
(d) The process liquid monitors shall normally be in service.
Adequate spare parts shall be on hand to allow necessary repairs to be made promptly. Alarms shall be set as specified in 6.4.1 (d).
Calibration of the " Radioactive Waste System Effluent to Canal" monitor shall be checked at least once a month.
Calibration of the remaining m9nitors shall be checked at least once every three months. Each day an anlysis shall be made of the previous 24-hour collection of discharge canal water.
(e) The area monitoring system shall normally be in operation; however, individual monitors may be taken out of service for maintenance and repairs. Adequate spare parts shall be on hand to allow necessary repairs to be made promptly. During monitor outages in normally accessible areas, temporary monitoring shall be provided if the remaining area monitors do not provide adequate coverage.
Calibration of monitors shall be checked at least monthly. Alarm trip points shall be set at a radiation level approximately twice the normal maximum indicated radiation level, but normally not less than one decade above the lowest scale reading.
Two films or TLDs, each with a sensitivity of 10mR, shall be provided at each site environmental monitoring station. During operation at stack release rates of 0.1 curie per second or less, at least five monitoring stations shall be provided. The films or TLDs at each station shall be replaced and analyzed at least monthly.
Operation at stack release rates above 0.1 curie per second shall not exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> without at least fifteen film or TLD monitoring stations in service. Two of these stations shall be on-site near the stack. The remaining additional stations shall complement the permanent stations but shall be located at greater distances from the stack. One film or TLD at each station shall be rplaced and analyzed at least every two weeks. The second film or TLD shall be replaced and analyzed monthly.
Under all stack release conditions, the film or TLD processor shall be instructed to report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on all films or TLDs that might indicate abnormal exposures.
(f) Gamma dose-rate measuring instruments and neutron dose-rate mesuring instruments shall be provided for establishing permissible working limits. These instruments shall be calibrated at least once every three months.
(g) At least two reactor water level indicators in the Reactor Depressurizing System shall be operable during power operation.
nu1281-0014c142 Amendment 43, 49 October 9,1981
6.9 3 (cont'd) f (b) Total number of samples.
(c) Humber of locations at which levels are found to be significantly above local backgrounds.
a (d) Highest, lowest, and the annual average concentrations or levels of radiation for the sampling point with the highest average and description of the location of that point with respect to the site.
(2) If levels of radioactive materials in environmental media indicate the likelihood of public intakes in excess of 1% _of those that could result from continuous annual exposure to the concentration values listed in Appendix B, Table II, Part 20, estimates of the likely resultant exposure to individuals and to population groups and assumptions upon which estimates are based shall be provided.
(3) If statistically significant variations of offsite environmental concer.trations with time are observed, correlation of these results with effluent release shall be provided.
6 9.4 Special Reports Special Reports shall be submitted to the Director of the appropriate Regional office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable technical specification section:
a.
In-service inspection reports.
c.
High range containment gamma monitoring system reports.
d.
Stack Gas ' Monitoring System Repo.-ts.
6.10 RECORD RETENTION (Records not previously req ired to be retained shall be retained as required below commencing January 1,1976. )
6.10.1 The following records shall be retained for at least five years; a.
Records and logs of facility operation covering time interval at each power level, Proposed 122
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