ML20039B240
| ML20039B240 | |
| 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 | |
| ML20039B235 | List: |
| References | |
| NUDOCS 8112220451 | |
| Download: ML20039B240 (6) | |
Text
.
PROPOSED TECIINICAL SPECIFICATION PAGE CHANGES Big Rock Point Plant nul081-0017c142 8112220451 011215 gDRADOCK 05000155 PDR
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 Depressurizing System to be used for detection of adequate core cooling during accident situations.
(e) The containment atmosphere shall be monitored by two high range, gamme monitors. The monitors are designed to measure gamma radiation in containment under accident conditions from 1 R/hr to 1E+06 R/hr. The monitors are located external to the containment sphere.
The readouts of the monitors are located in the control room.
l 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. Alarms normally shall be eet to annunicate 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 i
shall be taken monthly during power operation and analyzed for calibration of th? 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.
Adequate spare parts shall be on hand to allow necessary repairs to be made promptly. The alarm normally shall be set to annunciate 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 approxirately a factor of two above the expected stack release rate, but in no event above 0.47/E curies per second.
nu1281-0011d142 Proposed
64 6.4.3 (Contd)
The calibration of the system shall be checked c least monthly.
The particulate filter and iodine filter shall ae analyzed at least weekly.
(c) One of the emergency condenser vent monitors shall be in service at all times during power operatioe The monitors shall be set to 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 monitors 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.
nu1281-0011d142 Amendment No 43, 49 October 9, 1981
I 64a 6.4.3 -(Contd)
(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 bel.perable during power operation.
(h) Both high range containment atmosphere gamma monitors shall normally be in service during power operation.
If either monitor is 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 Specification 6.9.2, prepare and submit a Special Report tc the Commission pursuant to Specification 6.9.4 wP Sin the next 14 days outlining the cause'of the inoperability and che plans for restoring the system to OPERABII status. A channel check shall be performed for each monitor at least once per month, and channel calibration shall be
+
performed at each refueling outage.
9 nu1281-0011d142 Proposed
76b 7.6 (Contd)
Reference Procedure System or Function Frequency of Within These Undergoing Test Routine Tests Specifications Calibration of area One month or less Section 6.4.3 monitoring system Channel comparison check One month or less Section 6.4.3-of reactor level indicating instruments in the Reactor-Depressurization System Calibration of reactor At each major Section 6.4.3 level indicating instru-refueling shutdown ments in the reactor Depressurizing System Steam drum safety valve One month or less Section 4.1.2 position monitor check c
Calibration of steam drum At each major refueling Sectioc~4.1.2 j
safety valve position shutdown monitors High radiation trip At each major refueling Section 6.4.2 i
closure of the contain-shutdown ment ventilation isolation valves Channel Check of High Range One month or less Section 6.4.3 Containment Gamma Monitors Channel calibration of High At each major Section 6.4.3 Range Containment Gamma refueling shutdown j
Monitors 4
5 f
1 i
i nu1281-0011d142 Proposed i
!!.. - - - -..,. -. -.-..-..---.-.~., -..-....... -...,..-.. - -.. - -. - - - -.. -
6.9 3 (cont'd)
(b) Total number of samples.
(c) Humber of locations at which levels are found to be significantly above local backgrounds.
(d) Highest, lowest, and the annval 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, f
(3) If statistically significant variations of offsite environmental concentrations l
vith time are observed, correlation of these results with effluent release shall be provided.
6 9.h 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.
b.
Fire system reports.
c.
High range containment gamma monitoring system reports.
l l
6.10 RECORD RETENTION (Records not previously required 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.
P ror>s ed 122