ML110040862

Bellefonte Units 3 & 4 Cola (Final Safety Analysis Report), Rev. 3 - FSAR Chapter 04 Reactor - Sections 04.01 - 04.06

ML110040862
Person / Time
Site:	Bellefonte
Issue date:	12/22/2010
From:	Arent G Tennessee Valley Authority
To:	Document Control Desk, Office of New Reactors
Spink T
References
BELLEFONTE.P02.NP, BELLEFONTE.P02.NP.3, TENNVALLEY, TENNVALLEY.SUBMISSION.6, +reviewedmmc1
Download: ML110040862 (7)

Text

CHAPTER 4 REACTOR TABLE OF CONTENTS Section Title Page 4.1

SUMMARY

DESCRIPTION................................................................. 4.1-1 4.2 FUEL SYSTEM DESIGN..................................................................... 4.2-1 4.3 NUCLEAR DESIGN............................................................................. 4.3-1 4.4 THERMAL AND HYDRAULIC DESIGN .............................................. 4.4-1 4.4.7 COMBINED LICENSE INFORMATION......................................... 4.4-1 4.5 REACTOR MATERIALS...................................................................... 4.5-1 4.6 FUNCTIONAL DESIGN OF REACTIVITY CONTROL SYSTEMS...... 4.6-1 4-i Revision 3

CHAPTER 4 REACTOR 4.1

SUMMARY

DESCRIPTION This section of the referenced DCD is incorporated by reference with no departures or supplements.

4.1-1 Revision 3

4.2 FUEL SYSTEM DESIGN This section of the referenced DCD is incorporated by reference with no departures or supplements.

4.2-1 Revision 3

4.3 NUCLEAR DESIGN This section of the referenced DCD is incorporated by reference with no departures or supplements.

4.3-1 Revision 3

4.4 THERMAL AND HYDRAULIC DESIGN This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.

4.4.7 COMBINED LICENSE INFORMATION Replace the second paragraph in DCD Subsection 4.4.7 with the following:

COL 4.4-2 Following selection of the actual plant operating instrumentation and calculation of the instrumentation uncertainties of the operating plant parameters as discussed in DCD Subsection 7.1.6, the design limit DNBR values will be calculated. The calculations will be completed using the RTDP with these instrumentation uncertainties and confirm that either the design limit DNBR values as described in DCD Section 4.4 remain valid or that the safety analysis minimum DNBR bounds the new design limit DNBR values plus DNBR penalties, such as rod bow penalty.

This will be completed prior to fuel load.

4.4-1 Revision 3

4.5 REACTOR MATERIALS This section of the referenced DCD is incorporated by reference with no departures or supplements.

4.5-1 Revision 3

4.6 FUNCTIONAL DESIGN OF REACTIVITY CONTROL SYSTEMS This section of the referenced DCD is incorporated by reference with no departures or supplements.

4.6-1 Revision 3