ML050350301
| ML050350301 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/03/2005 |
| From: | NRC/NRR/DLPM |
| To: | |
| References | |
| TAC MC4278 | |
| Download: ML050350301 (3) | |
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 Not Used 5.6.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the Plant during the previous calendar year shall be submitted by May 15 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 Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period at 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 format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. 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.
5.6.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the plant during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant. 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 Part 50, Appendix I, Section IV.B.1.
(continued)
JAFNPP 5.6-1 Amendment 282
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Not Used 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) of Specification 3.2.1;
- 2. The MINIMUM CRITICAL POWER RATIO (MCPR) of Specification 3.2.2;
- 3. The LINEAR HEAT GENERATION RATE (LHGR) of Specification 3.2.3:
- 4. The Reactor Protection System (RPS) APRM Neutron Flux _
High (Flow Biased) Function Allowable Value of Table 3.3.1.1-1;
- 5. The Rod Block Monitor _ Upscale Function Allowable Value of Table 3.3.2.1-1; and
- 6. The Power/Flow Exclusion Region of Specification 3.4.1.
- b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and a pproved by the NRC, specifically those described in the following document:
- 1. NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel;
- 2. NEDC-31317P, James A. FitzPatrick Nuclear Power Plant SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis; and
- 3.
NEDO-31960-A, BWR Owners' Group Long-Term Stability Solutions Licensing Methodology.
The COLR will contain the complete identification for each of the Technical Specification referenced topical reports used to prepare the COLR (i.e.. report number, title, revision, date, and any supplements).
(continued)
JAFNPP 5.6-2 Amendment 282
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
(continued)
- 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.
5.6.6 PAM Report When a report is required by Condition B or F of LCO 3.3.3.1.
'Post Accident Monitoring (PAM) Instrumentation,* a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
OAFNPP 5.6-3 Amendment282