ML050400346
| ML050400346 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/07/2005 |
| From: | NRC/NRR/DLPM |
| To: | |
| Chernoff, H, NRR/DLPM, 301-415-4018 | |
| Shared Package | |
| ML050420115 | List: |
| References | |
| TAC MC4624, TAC MC4625 | |
| Download: ML050400346 (2) | |
Text
Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.
5.6.1 Deleted 5.6.2 Annual Monitoring ReDort
NOTE---------------------
A single submittal may be made that combines sections common to Units 1 and 2.
The Annual Monitoring Report covering the operation of the units during the previous calendar year shall be submitted by April 30 of each year.
The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.
The Annual Monitoring Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements. In the event that some individual 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 in a supplementary report as soon as possible.
The Annual Monitoring Report shall also include The Radioactive Effluent Release Report covering the operation of the units in the previous year and submitted in accordance with 10 CFR 50.36a.
The submittal shall combine sections 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. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.
Point Beach 5.6-1 Unit 1 -Amendment No. 216 Unit 2 - Amendment No. 221
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 Deleted 5.6.4 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) LCO 2.1.1, 'Safety Limits (SLs)"
(2) LCO 3.1.1, "Shutdown Margin (SDM)"
(3) LCO 3.1.3, "Moderator Temperature Coefficient (MTC)"
(4) LCO 3.1.5, "Shutdown Bank Insertion Limits" (5) LCO 3.1.6, 'Control Bank Insertion Limits" (6) LCO 3.2.1, "Heat Flux Hot Channel Factor (Fo(Z))"
(7) LCO 3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor(F NNH)'
(8) LCO 3.2.3, "Axial Flux Difference (AFD)"
(9) LCO 3.3.1, "Reactor Protection System (RPS) Instrumentation -
Overtemperature AT" (10) LCO 3.3.1, "Reactor Protection System (RPS) Instrumentation -
Overpower AT" (11) LCO 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits" (12) LCO 3.9.1, "Boron Concentration"
- b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC. When an initial assumed power level of 102 percent of the original rated thermal power is specified in a previously approved method, 100.6 percent of uprated rated thermal power may be used only when the main feedwater flow measurement (used as the input for reactor thermal output) is provided by the Caldon leading edge flowmeter (LEFM) as described in reports 11 and 12 listed below. When main feedwater flow measurements from the LEFM are unavailable, a power measurement uncertainty consistent with the instruments used shall be applied.
Future revisions of approved analytical methods listed in this Technical Specification that currently reference the original Appendix K uncertainty of 102 percent of the original rated thermal power should include the condition given above allowing use of 100.6 percent of uprated rated thermal power in the safety analysis methodology when the LEFM is used for main feedwater flow measurement.
Point Beach 5.6-2 Unit 1 - Amendment No. 216 Unit 2 - Amendment No. 221