ML17216A467
| ML17216A467 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/13/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML17216A468 | List: |
| References | |
| NUDOCS 8604080031 | |
| Download: ML17216A467 (5) | |
Text
DEFINITIONS STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist of:
a.
A test schedule for n systems, subsystems, trains or-other designated components obtained by dividing the specified test interval into n equal subintervals, and b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
THERtQL POh'ER 1.33 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNIDENTIFIED LEAKAGE 1.34 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.
UNRESTRICTED AREA 1.35 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
UNRODDED INTEGRATED RADIAL PEAKING FACTOR -
F 1.36 The UNRODDED INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak pin power to the average pin power in an unrodded core, excluding tilt.
UNRODDED PLANAR RADIAL PEAKING FACTOR Fxy 1.37 The UNRODDED PLANAR RADIAL PEAKING FACTOR is the maximum ratio of the peak to average power density of the individual fuel rods in any of the unrodded horizontal planes, excluding tilt.
ST.
LUCIE - UNIT 1
1-7 Amendment No.
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TABLE 1.1 FRE UENCY NOTATION NOTATION 4/M*
SA S/U N.A.
FRE(RUENCY At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> At least once per 7 days At least 4 per month at intervals of no greater than 9 days and a minimum of 48 per year At least once per 31 days At least once per 92 days At least once per 184 days At least once per 18 months Prior to each reactor startup Completed prior to each release Not,applicable
~ For Radioactive Effluent Sampling
- ",. For Radioactive Batch Releases Only ST.
LUCIE - UNIT 1 1-8 Amendment Nn.gy(,69
~
~
9 I
TABLE 1.2 OPERATIONAL MODES 2.
STARTUP 3.
HOT STANDBY 4.
HOT SHUTDOWN
> 0.99
. < 0.99
< 0.99 REACTIVITY MODE CONDITION, K 1.
POWER OPERATION
> 0.99
%RATED THERMAL POWER*
> 5l AVERAGE COOLANT TEMPERATURE
> 325'F
> 325'F
> 325'F 325'F
> Tavg
> 200'F 5.
COLD SHUTDOWN 6.
REFUELING**
I w 0.99
< 0.95
< 200'F
< 140'F c u 1ng ecay heat.
"*Fuel tn,the-reactnr vessel'-iHth.the'vessel'head closure bolts.less than
fully tensioned or with the'head removed..
ST.
LUCIE - UNIT 1 Amendment No. pp, 69 l
3/4.1 2 RADIOLOGICAL ENVIRONMENTAL MONITORING 3 4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be co'nducted as specified in Table 3.12-1.
APPLICABILITY:
At all times.
ACTION:
b.
With the radiological environmental monitoring program not being con-ducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.11, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
With the confirmed* level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar
- quarter, prepare and submit to the Comsission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and,3.11.2.3.
When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:
C.
concentration 1
+
concentration 2
+...
> 1.0 reporting level 1
repor ting level 2
When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.
This report shall include the methodology for calculating the cumulative, potential dose contributions for the calendar year from radionuclides detected in environmental samples and can be determined in accordance with the methodology and parameters in the ODCM.
This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and descr ibed in the Annual Radiological Environmental Operating Report.
With milk or broadleaf vegetation samples unavailable from one or more of the sample locations required by Table 3.12-1, identify locations
- A confirmatory reanalysis of the original, a duplicate, or a new sample may be desirable, as appropriate.
The results of the confirmatory analysis shall be completed at the earliest time consistent with the analysis but in any case
- .within 30 days.
ST.
LUCIE - UNIT 1 3/4 12-1 Amendment No. //4s69
RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION Continued ACTION:
(Continued) for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.
The specific loca-tions, from which samples were unavailable may then be deleted from the monitoring program.
Pursuant to Specification 6.9.1.10, identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a
revised figure(s) and table for the ODCM reflecting the new location(s).
d.
The provisions of Specifications.3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection, capabilities required by Table 4.12-1.
ST.
LUCIE <<UNIT 1
3/4 12-2 Amendment No. g'g,6~'