ML16343B044

From kanterella
Jump to navigation Jump to search
7 to Updated Final Safety Analysis Report, Chapter 14, Table 14.3.1-1, Plant Operating Range Analyzed by the Best-Estimate Large-Break LOCA Analysis for D. C. Cook Unit 2, Pages 1 - 2
ML16343B044
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 10/24/2016
From:
Indiana Michigan Power Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML16336A263 List: ... further results
References
AEP-NRC-2016-42
Download: ML16343B044 (2)


Text

INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Table: 14.3.1-1 Page:

1 of 2 Unit 2 Plant Operating Range Analyzed by the Best-Estimate Large-Break LOCA Analysis for D. C. Cook Unit 2 PARAMETER ANALYZED VALUE OR RANGE 1.0 Plant Physical Description a) Dimensions Nominal b) Pressurizer location On an intact loop(4) c) Hot assembly location Anywhere in core(1) d) Hot assembly type(2) 17xl7 V5 Fuel with ZIRLO' cladding, non-IFBA or IFBA e) Steam generator tube plugging level(5) 10%

f) Fuel assembly type(2) 17xl7 V5 Fuel with ZIRLO' cladding, non-IFBA or IFBA 2.0 Plant Initial Operating Conditions 2.1 Reactor Power a) Maximum Core power 3479.8 MWt b) Peak heat flux hot channel factor (FQ)(2)(5) 2.335 c) Peak hot rod enthalpy rise hot channel factor (FH)(2)(5) 1.644 d) Hot assembly radial peaking factor (PHA)(2) 1.644 / 1.04 e) Hot assembly heat flux hot channel factor (FQHA) 2.335 / 1.04 f) Axial power distribution (PBOT, PMID)(2)

Figure 14.3.1-2 g) Low power region relative power (PLOW)(2) 0.20 PLOW 0.70 h) Hot assembly burn up 75,000 MWD / MTU, lead rod(1)(3) i) MTC 0 at hot full power (HFP) j) Typical cycle length 18 months k) Minimum core average burn up(2) 10,000 MWD / MTU l) Maximum steady state depletion, FQ (2) 1.90 2.2 Fluid Conditions a) TAVG (5) 547.6 - 5.6ºF TAVG 578.1 + 4.1ºF

INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 25.0 Table: 14.3.1-1 Page:

2 of 2 Unit 2 Plant Operating Range Analyzed by the Best-Estimate Large-Break LOCA Analysis for D. C. Cook Unit 2 PARAMETER ANALYZED VALUE OR RANGE b) Pressurizer pressure 2,100 - 63 psia PRCS 2,100 + 63 psia 2,250 - 63 psia PRCS 2,250 + 63 psia c) Minimum thermal design flow 88,500 gpm / loop d) Upper head design THOT e) Pressurizer level (at hot full power) 59.8% of span (High TAVG) 40.0% of span (Low TAVG) f) Accumulator temperature(5) 60ºF TACC 120ºF g) Accumulator pressure 599.7 psia PACC 672.7 psia h) Accumulator liquid volume 921 ft3 VACC 971 ft3 i) Minimum accumulator boron 2228 ppm 3.0 Accident Boundary Conditions a) Minimum safety injection flow Table 14.3.1-4a and 14.3.1-4b b) Safety injection temperature(5) 70ºF SI Temp 105ºF c) Safety injection delay(5) 27 seconds (with offsite power) 54 seconds (with LOOP) d) Containment modeling See Figures 14.3.1-3 thru 14.3.1-9 and raw data in Tables 14.3.1-2, 14.3.1-3, & 14.3.1-7 e) Initial containment pressure See Table 14.3.1-2 f) Containment spray initiation delay See Table 14.3.1-2 g) Deck Fan initiation delay See Table 14.3.1-2 h) Single failure Loss of one ECCS train Notes:

1.

44 peripheral locations will not physically be lead power assembly.

2.

In the Westinghouse Reload Safety Analysis Checklist (RSAC) process, this parameter is identified as a key safety analysis parameter that could be impacted by a fuel reload.

3.

The fuel temperature and rod internal pressure data is only provided up to 62,000 MWD / MTU. In addition, the hot assembly / hot rod will not have a burn up this high in ASTRUM analyses.

4.

Analyzing the pressurizer as being located on an intact loop is limiting per Westinghouse methodology.

5.

Parameter values affected by evaluation described in Section 14.3.1.5.1