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MONTHYEARML0321902142003-08-0606 August 2003
09/22-23/2003 Meeting Announcement - 2003 U.S. Nuclear Regulatory Commission (NRC) Initial Exam Development Workshop
Project stage: Request
BSEP 03-0148, Request for License Amendment Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ration Safety Limits and Revision to References in Technical Specification 5.6.5, Core Operating Limits Report2003-10-31031 October 2003
Request for License Amendment Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ration Safety Limits and Revision to References in Technical Specification 5.6.5, Core Operating Limits Report
Project stage: Request
BSEP 04-0035, Response to RAI Regarding Technical Specification (Ts), 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limit and Revision to References in TS 5.6.5, Core Operating Limits Report (COLR)2004-03-0404 March 2004
Response to RAI Regarding Technical Specification (Ts), 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limit and Revision to References in TS 5.6.5, Core Operating Limits Report (COLR)
Project stage: Response to RAI
BSEP 04-0039, Response to RAI Regarding Technical Specification (TS) 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limit and Revision to References in TS 5.6.5, Core Operating Limits Report (COLR)2004-03-12012 March 2004
Response to RAI Regarding Technical Specification (TS) 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limit and Revision to References in TS 5.6.5, Core Operating Limits Report (COLR)
Project stage: Response to RAI
ML0408604212004-03-19019 March 2004
Response to Request for Additional Information Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limit and Revision to References in Technical Specification 5.6.5, Core Operating Limits Report (COLR)
Project stage: Response to RAI
ML0408503232004-03-19019 March 2004
Response to an Apparent Violation of Employee Discrimination Requirements (Us DOL Administrative Review Board Case No. 02-007)
Project stage: Other
ML0409000422004-03-26026 March 2004
Issuance of Amendment No. 231, Minimum Critical Power Ratio Safety Limit
Project stage: Approval
ML0408906732004-03-26026 March 2004
Technical Specification Pages 2.0-1 and 5.0-20, Amendment No. 231 Re. Minimum Critical Power Ratio Safety Limit
Project stage: Other
ML0407708982004-03-29029 March 2004
Global Nuclear Fuel, Request for Withholding Information from Public Disclosure, Brunswick Steam Electric Plant, Unit 1
Project stage: Withholding Request Acceptance
ML0407605712004-03-31031 March 2004
Global Nuclear Fuel, Request for Withholding Information from Public Disclosure, Brunswick, Unit 1
Project stage: Withholding Request Acceptance
ML0409602922004-04-0101 April 2004
RAI, Request for Withholding Information from Public Discolsure, TAC MC1249
Project stage: RAI
ML0411106462004-04-19019 April 2004
Withholding from Public Disclosure, Information Reference in CP&L Letter, Serial No. BSEP 04-0043, Brunswick Steam Electric Plant, Unit No. 1, Docket No. 50-325/License No. DPR-71, Request for Additional Information
Project stage: RAI
2004-03-26
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Text
SLs 2.0 2.0 SAFETY LIMITS (SLS) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10%
rated core flow:
THERMAL POWER shall be < 23% RTP.
2.1.1.2 With the reactor steam dome pressure 2 785 psig and core flow 2 10%
rated core flow:
MCPR shall be 2Ž1.11 for two recirculation loop operation or 2 1.12 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active
- irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be < 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.
Brunswick Unit 1 2.0-1 Amendment No. 231
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1.
The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) for Specification 3.2.1;
- 2.
The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.2.2;
- 3.
The period based detection algorithm (PBDA) setpoint for Function 2.f, Oscillation Power Range Monitor (OPRM) Upscale, for Specification 3.3.1.1; and
- 4.
The Allowable Values and power range setpoints for Rod Block Monitor Upscale Functions for Specification 3.3.2.1.
- b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1.
NEDE-2401 1-P-A, "General Electric Standard Application for Reactor Fuel" (latest approved version).
- 2.
NEDE-32906P-A, "TRACG Application for Anticipated Operational Occurrences (AOO) Transient Analyses," approved version as specified in the COLR.
- c.
The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d.
The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
(continued)
Brunswick Unit 1 5.0-20 Amendment No. 231
