ML20011D299
| ML20011D299 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 12/21/1989 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20011D295 | List: |
| References | |
| NUDOCS 8912260139 | |
| Download: ML20011D299 (4) | |
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- m JPROPOSED TEGINICAL FPFCIFICATION' PAGE CHANGES F
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72 7.3.2 (Contd)
(e) Critical approaches shall be monitored using the source range
/
monitors. The start-up rate shall be restricted to demonstrate
/
that the power range monitors overlap the source range monitors
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prior to the source range monitogs going offseale or saturated.
/
A one decade overlap prior to 10 counts per second on the
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source range monitors is normal and satisfactory for control
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and safety purposes before continuing further into the power
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range.. Control rod withdrawal sequence shall be specified and
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limited to those sequences shown by previous analysis or tests
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to preserve fuel integrity in the event of accidental reactivity
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insertion either while starting up or at power.
/
(f) The power shall be adjusted once criticality is reached to maintain a reactor vessel temperature rise rate not to exceed 100*F per hour.
(g) The turbine shaft sealing system shall be placed in service as soon as sufficient steam pressure is available (approximately 150 psig).
(h) The condenser shall be evacuated with the mechanical vacuum pump and the air ejector will be placed in service.
(i) Turbine. heating shall be started during this operation sequence.
After turbine heating is completed, the turbine shall be gradually brought up to speed.
(j) The mode of turbine control shall be transferred to the initial pressure regulator.
(k) The control rods shall be adjusted to provide the desired power i
distribution within the core.
7.3.3 Hot Start-Up Whenever the plant has been shut down for a period of time with the reactor vessel and auxiliaries remaining pressurized, a hot start-up procedure shall be followed to return the plant to service. This procedure will be essertially independent of the cause of shutdown assuming that the cause is recognized and any nonstandard conditions have been corrected. The reactor instrumentation shall be reset and downscaled and a hot start-up checklist shall be completed prior to I
the withdrawal of control rods.
A coupling integrity check shall be made in accordance with Section 5.2.2(d).
The start-up shall then proceed in accordance with Paragraphs (d) through (k) of Section 7.3.2 of the normal cold start-up procedure outlined above.
Proposed TSB 1289-0236-NLO4-M.02
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54 6.1.2.1 Source Range Monitor Channel - Channels 6 and 7 shall provide logarithmic neutron flux level and period information from source level to seven decades above source level, without moving 10 to go 3% of rated power)..The detectors (approximately 10 principal components in each channel shall be a neutron detector, current pulse amplifier, source range monitor instrument, log count rate meter, log count rate recorder and period meter. Gas-filled Boron-10 lined proportional counters with a sensitivity of approximately 12 counts /nv shall be used as detectors. "rovisions shall be made for remotely positioning the detectors.
By moving the detectors away from the midplane of the core, their effective range may be extended. A short period on either channel shall be annunciated in the control room.
6.1.2.2 Deleted 6.1.2.3 Power Range Monitor Channel - Channels 1, 2 and 3 shall provide logarithmic neutron flux level information and period scram
-7 protection from approximately 1 x 10 % to 1% rated power and linear neutron flux level information from approximately 1% to 150%
rated power for the 84 fuel bundle core. The principal components in each channel shall be a neutron detector, DC-wide range monitor, power level recorder and operatar display assembly which indicates
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power level and period.
The detectors shall be gamma compensated ion chambers with a design sensitivity of at least 2.2 x 10~l4 amperes /nv.
The channel output shall be connected to the reactor safety system to provide high neutron flux and short period scram protection.
6.1.2.4 In-Core Flux Monitors - In-core flux monitors shall be used to evaluate predicted power distributions and detect power oscillations or deviations from expected power distributions in time for the operator to take corrective action to avoid exceeding local heat flux limits.
6.1.2.5 Deleted Proposed
'TSB1289-0236-NLO4-NLO2
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ADMINISTRATIVE CONTROLS 6.10.2 (Contd) k.
Records for environmental qualifications which are covered under the
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provisions of 10CFR50.49.
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Recordg89 training and qualification for members of the Plant f
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i Staff.
Records of reactor tests and experiments.(#
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6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR, Part 20, and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
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(a)Povement of items 6.10.21 and m from section 6.10.1 increased the length of time for which records must be retained from five years to the duration of the operating licepre. Since-these changes in record keeping will begin on or about January 1,1984, records of these two types created af ter December 31, 1978 will be retained for the duration of the operating license.
Retention for the duration of the operating license will not be required for records of these two types created before January 1, 1979.
122 Proposed TSB1289-0236-NLO4-NLO2
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