ML072180219

Technical Specifications, Revises TS 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) to Add the Ferret Code as an Approved Methodology for Determining RCS Pressure and Temperature Limits

ML072180219
Person / Time
Site:	Point Beach
Issue date:	10/18/2007
From:	NRC/NRR/ADRO/DORL/LPLIII-1
To:
Cushing J, NRR/DLPM/LPDIV-2,415-1424
Shared Package
ML072180204	List: ML072180191 ML072180219
References
TAC MD3800, TAC MD3801
Download: ML072180219 (1)

Text

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, hydrostatic testing, LTOP enabling, and PORV lift settings as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

(1) LCO 3.4.3, "RCS Pressure and Temperature (P/T) Limits" (2) LCO 3.4.6, "RCS Loops-MODE 4" (3) LCO 3.4.7, "RCS Loops-MODE 5, Loops Filled" (4) LCO 3.4.10', "Pressurizer Safety Valves" (5) LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP)"

b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the NRC Letters dated October 6, 2000, July 23, 2001, and October 18, 2007.

c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

5.6.6 PAM Report When a report is required by Condition B or F of LCO 3.3.3, "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.

5.6.7 Tendon Surveillance Report Abnormal conditions observed during testing will be evaluated to determine the effect of such conditions on containment structural integrity. This evaluation should be completed within 30 days of the identification of the condition. Any condition which is determined in this evaluation to have a significant adverse effect on containment structural integrity will be considered an abnormal degradation of the containment structure.

Any abnormal degradation of the containment structure identified during the engineering evaluation of abnormal conditions shall be reported to the Point Beach 5.6-5 Unit 1 - Amendment No. 229 Unit 2 - Amendment No. 234