ML070510312
| ML070510312 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/15/2007 |
| From: | NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | |
| P. Milano X1457 | |
| Shared Package | |
| ML063450067 | List: |
| References | |
| TAC MD3380, TAC MD3381 | |
| Download: ML070510312 (8) | |
Text
Definitions 1.1 1.1 Definitions CHANNEL OPERATIONAL TEST (COT)
CORE OPERATING LIMITS REPORT (COLR)
DOSE EQUIVALENT 1-131 E - AVERAGE DISINTEGRATION ENERGY A COT shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping, or total channel steps.
The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.4. Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT 1-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in Table 2.1 of Federal Guidance Report No. 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion,"
September 1988.
E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives > 15 minutes, making up at least 95% of the total noniodine activity in the coolant.
Point Beach 1.1-2 Unit 1 -Amendment No. 224 Unit 2 - Amendment No.
230
CREFS Actuation Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Control Room Emergency Filtration System (CREFS) Actuation Instrumentation LCO 3.3.5 The CREFS actuation instrumentation for each Function in Table 3.3.5-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.5-1.
ACTIONS Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more Functions A.1 Place CREFS in the 7 days inoperable, emergency mode of operation.
B.
Required Action and NOTE----------
associated Completion Required Action B.1 is not Time not met.
applicable for inoperability of the Containment Isolation actuation function.
B.1 Suspend movement of Immediately irradiated fuel assemblies.
AND (continued)
Point Beach 3.3.5-1 Unit 1 - Amendment No.
Unit 2 - Amendment No.
224 230
CREFS Actuation Instrumentation 3.3.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
B.2 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND B.3 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS NOTE-------------------------------
Refer to Table 3.3.5-1 to determine which SRs apply for each CREFS Actuation Function.
SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.2 Perform COT.
92 days SR 3.3.5.3 Perform CHANNEL CALIBRATION.
18 months Point Beach 3.3.5-2 Unit 1 - Amendment No.
Unit 2 - Amendment No.
224 230
CREFS Actuation Instrumentation 3.3.5 Table 3.3.5-1 (page 1 of 1)
CREFS Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE TRIP FUNCTION CONDITIONS CHANNELS REQUIREMENTS SETPOINT Control Room Radiation
- a. Control Room Area Monitor 1, 2, 3, 4, 1
SR 3.3.5.1 NA (a)
SR 3.3.5.2 SR 3.3.5.3
- b. Control Room Air Intake 1, 2, 3, 4, 1
SR 3.3.5.1 NA (a)
SR 3.3.5.2 SR 3.3.5.3
- 2.
Containment Isolation Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3, for all initiation functions and requirements.
(a)
During movement of irradiated fuel assemblies.
Point Beach 3.3.5-3 Unit 1 - Amendment No.
224 Unit 2 - Amendment No.
230
CREFS 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Control Room Emergency Filtration System (CREFS)
LCO 3.7.9 CREFS shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, 4, During movement of irradiated fuel assemblies ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
A.1 Restore CREFS to 7 days OPERABLE status.
B.
Required Action and B.1 Suspend movement of Immediately associated Completion irradiated fuel Time not met.
assemblies.
AND B.2 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND B.3 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Point Beach 3.7.9-1 Unit 1 - Amendment No.
224 Unit 2 - Amendment No.
230
Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the limit specified in the COLR.
APPLICABILITY:
MODE 6.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Boron concentration not A.i Suspend positive Immediately within limit, reactivity additions.
AND A.2 Initiate action to restore Immediately boron concentration to within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> specified in the COLR.
Point Beach 3.9.1-1 Unit 1 - Amendment No.
224 Unit 2 - Amendment No.
230
Nuclear Instrumentation 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two source range neutron flux monitors shall be OPERABLE.
AND One source range audible count rate circuit shall be OPERABLE.
APPLICABILITY:
MODE 6.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One required source A.1 Suspend positive Immediately range neutron flux reactivity additions.
monitor inoperable.
B.
Two required source B.1 Initiate action to restore Immediately range neutron flux one source range monitors inoperable, neutron flux monitor to OPERABLE status.
AND B.2 Perform SR 3.9.1.1.
Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C.
Required source range C.1 Initiate action to isolate Immediately audible count rate circuit unborated water inoperable, sources.
Point Beach 3.9.2-1 Unit 1 - Amendment No. 224 Unit 2 - Amendment No. 230
Refueling Cavity Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Refueling Cavity Water Level LCO 3.9.6 APPLICABILITY:
Refueling cavity water level shall be maintained > 23 ft above the top of reactor vessel flange.
During movement of irradiated fuel assemblies within containment.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Refueling cavity water A.1 Suspend movement of Immediately level not within limit, irradiated fuel assemblies within containment.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify refueling cavity water level is > 23 ft 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> above the top of reactor vessel flange.
Point Beach 3.9.6-1 Unit 1 - Amendment No. 224 Unit 2 - Amendment No.
230