ML021550282
| ML021550282 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/30/2002 |
| From: | NRC/NRR/DLPM |
| To: | |
| References | |
| Download: ML021550282 (5) | |
Text
Definitions 1.1 1.1 Definitions (continued)
CHANNEL FUNCTIONAL TEST CORE ALTERATION A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, trip functions, and channel failure trips.
The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.
CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.
The following exceptions are not considered to be CORE ALTERATIONS:
- a.
Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);
and
- b.
Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle.
These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5.
Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, CORE OPERATING LIMITS REPORT (COLR)
DOSE EQUIVALENT 1-131 (continued)
Amendment No.
221 I I
1.1-2 Brunswick Unit 1
Definitions 1.1 1.1 Definitions DOSE EQUIVALENT 1-131 (continued)
EMERGENCY CORE COOLING SYSTEM (ECCS)
RESPONSE
TIME ISOLATION INSTRUMENTATION RESPONSE TIME LEAKAGE Submersion, and Ingestion," 1989 and FGR 12, "External Exposure to Radionuclides in Air, Water, and Soil," 1993.
The ECCS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS initiation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays, where applicable.
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
The ISOLATION INSTRUMENTATION RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves receive the isolation signal (e.g.,
de-energization of the MSIV solenoids).
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
LEAKAGE shall be:
- a.
Identified LEAKAGE
- 1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or
- 2.
LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; (continued)
Amendment No.
221 1 Brunswick Unit 1 1.1-3
Definitions 1.1 1.1 Definitions (continued)
CHANNEL FUNCTIONAL TEST CORE ALTERATION A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, trip functions, and channel failure trips.
The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.
CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.
The following exceptions are not considered to be CORE ALTERATIONS:
- a.
Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);
and
- b.
Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle.
These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5.
Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present.
The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, CORE OPERATING LIMITS REPORT (COLR)
DOSE EQUIVALENT 1-131 (conti nued)
Amendment No. 246 I I
1.1-2 Brunswick Unit 2
Definitions 1.1 1.1 Definitions DOSE EQUIVALENT 1-131 (continued)
EMERGENCY CORE COOLING SYSTEM (ECCS)
RESPONSE
TIME ISOLATION INSTRUMENTATION RESPONSE TIME LEAKAGE Submersion, and Ingestion," 1989 and FGR 12, "External Exposure to Radionuclides in Air, Water, and Soil," 1993.
The ECCS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS initiation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays, where applicable.
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
The ISOLATION INSTRUMENTATION RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves receive the isolation signal (e.g.,
de-energization of the MSIV solenoids).
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
LEAKAGE shall be:
- a.
Identified LEAKAGE
- 1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or
- 2.
LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; (continued)
Amendment No.
246 I Brunswick Unit 2 1.1-3
APPENDIX B Additional Conditions Amendment Number Additional Conditions Implementation Date 233 The licensee is authorized to relocate certain requirements included in Appendix A and the former Appendix B to licensee-controlled documents. Implementation of this amendment shall include the relocation of these requirements to the appropriate documents, as described in the licensee's letters dated November 1, 1996, October 13, 1997, February 26, 1998, April 24, 1998, and May 22, 1998, evaluated in the NRC staff's Safety Evaluation enclosed with this amendment.
The End-Of-Cycle Recirculation Pump Trip system instrumentation shall be maintained inoperable (i.e. manually bypassed) during Mode 1, when thermal power is greater than or equal to 30%
rated thermal power. Implementation of this amendment shall include this condition, as described in the licensee's letter dated March 13, 1998, evaluated in the NRC staff's Safety Evaluation enclosed with this amendment.
The licensee shall, consistent with the applicable provisions of the BWR Owners' Group Report NEDC-31858P, Revision 2, as approved in the NRC staff's Safety Evaluation dated March 3, 1999, complete the seismic verification walkdowns and modifications necessary to ensure seismic ruggedness of the alternate leakage treatment (ALT) piping and appendages.
The licensee shall, consistent with the licensee's letter dated September 27, 2001 (i.e., Serial:
BSEP 01-0112), include ALT path motor-operated valves MS-F038A, MS-F038B, MS-F038C, MS-F038D, and MVD-F021 in an augmented inservice testing program.
The licensee shall, consistent with the licensee's letter dated September 27, 2001 (i.e., Serial:
BSEP 01 -0112), include ALT path check valves MVD-V5008 and MVD-V5009 in the facility check valve program.
Amendment No. 246 This amendment is effective immediately and shall be implemented within 90 days of the date of this amendment.
This amendment is effective immediately and shall be implemented within 90 days of the date of this amendment.
Prior to startup following the Unit 2 Cycle 16 Refueling Outage.
Prior to startup following the Unit 2 Cycle 16 Refueling Outage.
Prior to startup following the Unit 2 Cycle 16 Refueling Outage.
233 246 246 246