ML20247H244
| ML20247H244 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/27/1989 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20247H241 | List: |
| References | |
| NUDOCS 8905310195 | |
| Download: ML20247H244 (3) | |
Text
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REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be:
~4 a.
Less positive than 0.5x10 ok/k/ F whenever THERMAL POWER is 570% of RATED THERMAL POWER, u.
Less positive than 0.0 x ak/k/ F whenever THERMAL POWER is
>70% of RATED THERMAL POWER, and
~4 c.
Less negative than -3.4x10 Ak/k/ F at RATED THERMAL POWER.
APPLICABILITY:
MODES 1 and 2*#
ACTION:
With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.1.4.1 The MTC shall be determined to be within its limits by confirmatory measurements.
MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.
4.1.1.4.2 The MTC shall be determined at the following frequencies and THERMAL POWER conditions during each fuel cycle:
a.
Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.
b.
At any THERMAL POWER, prior to reaching a RATED THERMAL POWER equilibrium boron concentration of 800 ppm.
c.
At any THERMAL POWER, within 14 EFPD after reaching a RATED THERMAL POWER equilibrium boron concentration of 300 ppm.
- With K 21.0.
eff
- See Special Test Exception 3.10.2.
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8905310195 890427 PDR ADOCK 05000368 P
PNV ARKANSAS - UNIT 2 3/4 1-5 Amendment No. 24, 80, BZ
REACTIVITY CONTROL SYSTEMS CEA DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) CEA drop time, from a fully withdrawn position, shall be 5 3.2 seconds from when the electrical power is interrupted to the CEA drive mechanism until the CEA reaches its 90 percent insertion position with:
T,yg 2 525 F, and a.
b.
All reactor coolant pumps operating.
APPLICABILITY: MODES 1 and 2.
ACTION:
a.
With the drop time of any full length CEA determined to exceed the above limit, restore the CEA drop time to within the above limit prior to proceeding to MODE 1 or 2.
b.
With the CEA drop times within limits but determined at less than full reactor coolant flow, operation may proceed provided THERMAL POWER is restricted to less than or equal.to the maximum THERMAL POWER level allowable for the reactor coolant pump combination operating at the time of CEA drop time determination.
StJRVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality:
a.
For all CEAs following each removal of the reactor vessel
- head, b.
For specifically affected individual CEAs following any l
maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c.
At least once per 18 months.
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ARKANSAS - UNIT 2 3/4 1-23 AMENDMENT N0. 84 l
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L ADMINISTRATIVE CORJ,RL.
ANNUAL RADIOLOGIr.. ENVIRONMENTAL OPERATING REPORT
- 6.9.4 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of year.
a.
The annual radiological environmental operating report shall include summaries, interpretations, and an analysis of trends of the results oT the radiological environmental surveillance activities for the report period,. including a comparison with preoperational studies, operational controls (as appropriate),
and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.
The reports shall also include the results of land use censuses required by Specification 3.12.2.
If harmful effects or evidence of irreversible damage are detected by the l
monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
b.
The annual radiological environmental operating reports shall include summarized and tabulated results of all radiological environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
c.
The report shall also include the following:
a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3.
- A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
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ARKANSAS - UNIT 2 6-21 AMENDMENT N0. 50
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