ML032190038

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Technical Specification Pages 5.6-8 & 5.6-9 to Amendment Nos. 259 & 236
ML032190038
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 08/06/2003
From: Vissing G
NRC/NRR/DLPM/LPD1
To: Vanderheyden G
Calvert Cliffs
References
TAC MB5416, TAC MB5417
Download: ML032190038 (2)


Text

Reporting Requirements 5.6 5.6 Reporting Requirements ii. CEN-119(B)-P, "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit 1 and Unit 2"l iii. Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7, 1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket 50-318, Request for Amendment, Unit 2 Ninth Cycle License Application" iv. Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10, 1990, "Safety Evaluation Report Approving Unit 2 Cycle 9 License Application"

42. Letter from Mr. D. G. McDonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995, "Approval to Use Convolution Technique in Main Steam Line Break Analysis - Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (TAC Nos. M90897 and M90898)
43. CENPD-387-P-A, "ABB Critical Heat Flux Correlations for PWR Fuel"
44. CENPD-199-P, Supplement 2-P-A, Appendix A, CE Setpoint Methodology"
45. CENPD-404-P-A, "Implementation of ZIRLOm Cladding Material in CE Nuclear Power Fuel Assembly Designs"
46. CENPD-132, Supplement 4-P-A, "Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model"
47. CENPD-137, Supplement 2-P-A, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model"
c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, ECCS limits, nuclear limits such as CALVERT CLIFFS - UNIT 1 5.6-8 Amendment No. 259 CALVERT CLIFFS - UNIT 2 Amendment No. 236

Reporting Requirements 5.6 5.6 Reporting Requirements SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Not Used 5.6.7 Post-Accident Monitoring Report When a report is required by Condition B or G of LCO 3.3.10, "Post Accident Monitoring 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.

5.6.8 Tendon Surveillance Report Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.

5.6.9 Steam Generator Tube Inspection Renort

a. Following each inservice inspection of steam generator tubes, the number of tubes plugged or repaired in each steam generator shall be reported to the NRC within 15 days.

CALVERT CLIFFS - UNIT 1 5.6-9 Amendment No. 259 CALVERT CLIFFS - UNIT 2 Amendment No. 236