ML061420498
| ML061420498 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 05/04/2006 |
| From: | Plant Licensing Branch III-2 |
| To: | |
| Martin R, NRR/DORL, 415-1493 | |
| Shared Package | |
| ML060180054 | List: |
| References | |
| TAC MC9155 | |
| Download: ML061420498 (4) | |
Text
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE Review.................................................................................................
6-7 Audits...................................................................................................
6-8 Authority...............................................................................................
6-8 Records................................................................................................
6-9 6.5.3 TECHNICAL REVIEW AND CONTROL Activities...............................................................................................
6-9 6.6 REPORTABLE EVENT ACTION......................................................................
6-10 6.7 SAFETY LIMIT VIOLATION.............................................................................
6-10 6.8 PROCEDURES AND PROGRAMS..................................................................
6-11 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS Startup Report.........................................................
6-13 Annual Report..............
6-13 Annual Radiological Environmental OperatingReport...........................
6-14 Annual Radioactive Effluent Release Report........................................
6-14 Not Used..............................................................................................
6-16 Core Operating Limits Report...............................................................
6-16 6.9.2 SPECIAL REPORTS...........................................................................
6-17 6.10 RECORD RETENTION.................................................................................
6-17 6.11 RADIATION PROTECTION PROGRAM........................................................
6-18 6.12 HIGH RADIATION AREA...............................................................................
6-18 SUMMER - UNIT 1 XIX Amendment No. 175
ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Tite 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator Office of Inspection and Enforcement unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
6.9.1.2 The startup report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions an specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary repckts shall be submitted at leaist eveiy three months until all three events have been completed.
ANNUAL REPORT 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 31 of each year. The initial report shall be submitted prior to March 31 of the year following initial criticality.
6.9.1.5 Not used.
SUMMER - UNIT I 6-13 Amendment No. 17 5
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 The annual radiological environmental operating report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.
The report shall include summaries, interpretations, and an analysis 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 (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
6.9.1.7 Not used.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 Annual radioactive effluent release report covering the operation of the unit during the previous calendar year shall be submitted prior to May I of each year.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
SUMMER - UNIT 1 6-14 Amendment No. 17 5
ADMINISTRATIVE CONTROLS 6.9.1.9 Not used.
6.9.1.10 Not used.
CORE OPERATING LIMITS REPORT 6.9.1.11 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:
- a.
Moderator Temperature Coefficient BOL and EOL Limits and 300 ppm surveillance limit for Specification 3/4.1.1.3,
- b.
Shutdown Rod Insertion Limit for Specification 3/4.1.3.5,
- c.
Control Rod Insertion Limits for Specification 3/4.1.3.6,
- d.
Axial Flux Difference Limits, target band, and APLND for Specification 3/4.2.1,
- e.
Heat Flux Hot Channel Factor, F*TP, K(z), W(z), APLND, W(Z)BL, and FQ(Z) manufacturing/measurement uncertainties for Specification 3/4.2.2,
- f.
Nuclear Enthalpy Rise Hot Channel Factor, FRTH, Power Factor Multiplier, PFAH, and FN measurement uncertainties limits for Specification 3/4.2.3.
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:
- a.
WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (W Proprietary).
SUMMER - UNIT I 6-16 Amendment No. 175