ML20041F365
| ML20041F365 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/10/1982 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20041F350 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NUDOCS 8203160431 | |
| Download: ML20041F365 (6) | |
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PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES Big Rock Point Plant 8200:160431 820310 gDRADOCK 05000155 PDR nu0282-0028d142
60 6.3.2 Refueling Operation Controls Interlocks shall be provided to prevent all motion with any of the refueling cranes (namely, jib cranes, transfer cask winch) which are positioned over the reactor vessel whenever any control rod is not fully inserted in the core and the mode selector switch is in the " refuel" position.
6.3.3 Operating Requirements (a) All reactor refueling safety system sensors and trip devices shall be functionally tested at each major refueling shutdown and shall be maintained in the specified condition during all refueling operations.
(b) The refueling operation controls including position interlocks shall be functionally tested at each major refueling shutdown.
6.4 PLANT MONITORING SYSTEMS The plant monitoring systems include the process radiation monitoring systems, the area monitoring system, and the reactor water level monitors in the Reactor Depressurizing System, and the containment pressure and level monitors.
6.4.1 Process Radiation Monitoring Systems The process radiation monitoring systems consist of the air ejector off-gas monitoring system including the fuel rupture detection system; stack gas monitoring system, the emergency condenser vent monitor, and process liquid monitor system.
(a) Air Ejector Off-Gas Monitoring Systems Continuous monitoring of the air ejector off-gas radioactivity shall be provided by either two ion chamber type systems or two l
single-channel gamma scintillation spectrometer systems designed l
to detect noble gas fission products indicative of a fuel element rupture. One system (either ion chamber or scintillation detector) will always be in service with an identical system as an operational spare. The sampling system shall be designed to hold up the gas sample to allow time for the decay of Nitrogen-16 and other short-lived activation gases. The off gas monitoring channels shall be calibrated so that the indicated and recorded count rate output of the channel in service, combined with the off gas flow Permits detemination of the fission gases discharge 24 rate from 10 to 10 curies per second at the stack. A trip circuit in the air ejector off gas monitor shall have an alarm which shall annunciate in the control room. The air ejector off-gas monitor trip circuit shall also initiate action of a time-delay switch, which in turn shall trip the off-gas shutoff valve closed after a preselected delay adjustable up to 15 minutes.
Alarm and trip settings shall be as specified in Section 6.4.3(a).
nu0282-0026d142 Proposed l
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62 The radioactive waste system effluent to canal channel shall be used in conjunction with the liquid waste disposal system. Each batch of liquid wastes to be discharged shall be analyzed prior to discharge as described in 6.5.
This monitor shall provide an additional means of checking the activity of the wastes being discharged..
The circulating water discharge monitor shall monitor the main stream of plant effluent prior to its discharge into Lake Michigan, and serve as a backup to the other liquid monitors.
In addition, a continuous sample is drawn from the discharge canal for periodic analysis as specified in 6.4.3(d).
(e)
In-Plant Radio-Iodine Measurements Under Accident Conditions Procedures for determining airborne radio-iodine concentrations in occupied areas shall be implemented and technicians shall be trained on an annual basis. Maintenance of the sampling equipment shall occur at least semi-annually and maintenance of the analytical equipment shall occur at least monthly.
6.4.2 Area Monitoring System, Reactor Water Level Monitors and Containment Monitors (a) Nineteen fixed gamma monitors employing scintillation type detectors shall be installed throughout the plant, and each shall have the following:
(i)
A range consistent with expected radiation levels in the area to be monitored.
(0.01 mr to 10 mr or 0.1 mr to 100 mr or 1 mr to 1,000 mr.)
(ii) An output indicated and recorded in the control room.
(iii An adjustable high radiation alarm which shall be annunciated in the control room. Alarm settings that shall be as indicated in 6.4.3(e).
(b) Two of these nineteen area monitors shall be located in the vicinity of the fuel storage areas to provide gamma monitoring of the fuel storage areas and refueling operations.
Local alarms shall be provided for these monitors, and alarm setting shall be in accordance with the provisions of 10 CFR 70.
In the event that both of these monitors become inoperable during power operation or fuel handling activities, the containment ventilation isolation valves shall be closed.
However, notwithstandi: g the requirements of Section 70.24(a)(1),
alarm settings may be raised above 20 mR/hr as long as the overall detection criterion in Section 70.24(a)(1) is satisfied and the requirements specified in paragraph 6.4.3(e) below are met.
nu0282-0026e142 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 Depressurizing System to be used for detection of adequate core cooling during accident situations.
(e) Two containment pressure monitors and two containment level monitors are provided in the main control room for accident monitoring.
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 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 (af ter 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.
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 approximately 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 system shall be checked at least monthly.
The particulate filter and iodine filter shall be analyzed at least weekly.
(c) One of the emergency condenser vent monitors shall be in service at all times during power operation. 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.
nu0282-0026d142 Proposed
'64a 6.4.3 (Contd)
(h) Two containment pressure monitors and two containment level monitors shall be operable during power operation. Plant shutdown is required within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following a 7 day period when one monitor of either type is inoperable.
Plant shutdown is required within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period when both monitors of one type are inoperable.
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l nul081-0016d142 Proposed i
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 Calibration of steam drum At each major refueling Section 4.1.2 safety valve position shutdown monitors High radiation trip At each major refueling Section 6.4.2 closure of the contain-shutdown ment ventilation isolation valves Calibration of contain-At each major Section 6.4.3 ment water level monitors refueling shutdown l
and containment pressure monitors I
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nu0282-0026d142 Proposed 1
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