ML23129A264

1 to Updated Safety Analysis Report,Section I, Figures

ML23129A264
Person / Time
Site:	Cooper
Issue date:	04/20/2023
From:	Nebraska Public Power District (NPPD)
To:	Office of Nuclear Reactor Regulation
Shared Package
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References
NLS2023022
Download: ML23129A264 (1)

Text

Legend

1. = Flow, lbm/hr H = Enthalpy, Btu/lbm F = Temperature, °F M = Moisture, %

P = Pressure, psia Wd= 100 %

520.5 H 527.2 Of

~h =0.7 H 1020

',, \\

p 2419 MWt Total Core Flow 73.5E+06 Main Steam Flow Carryunder = 0.22%

9.707E+o6 #

• 1191.5 H

• 0.39 M

• 968 P

• Main Feed Flow

,$.772E+o6 #

341.8 H 367.7 °F 9.672E+o6 #

341.1 H 367.1 °F J,tl l.000E+05 #

407.6 H 429.2 °F Core Thennal Power Pump Heating Cleanup Losses Other Szstem Losses Turbine Cycle Use 3.500E+-04 #

68.0 H 97.2 °F Control Rod Drive Feed Flow Cleanup Demineralizer System I.000E+05 #

519.8 H 526.6 °F

• Conditions at upstream side ofTSV 2419.0 7.4

-3.3

-0.6 2422.5 MWt Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Reactor Heat Balance - Rated Figure I-1-1 08/07/08

r---,

I SAFETY I

I smEIIA I

L ___ J PROTECTIVE ACTION A r---,

I CORE I

I SPRAY I

L~ST~_J 1

PUMPIATER TO CORE rs"AFErv-,

I SYSTEM B I

I I

L.

_J PROTECTIVE ACTION B SAFETY ACTION CONCEPT

,-;;D-;-,

I A-C I

I POWER I

L.J!r..J PROVIDE A-C POIER CORE STBY.

COOLING (LOI PRESSURE)

EXAMPLE I

SAFETY I

I SYSTEM C I L ___ --'

1 PROTECTIVE ACTION C PUIIPIATER TO CORE Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Relationship Between Safety Action and Protective Action Figure I-2-1

PROTECTIVE FUNCTION A SAFETY SYSTEM INTRA-SYSTEM ACTIONS PROTECTIVE ACTION CONCEPT PROTECTIVE FUNCTION B HIGH PRESSURE COOLANT INJECTION SYSTEM HIGH DRYIELL PRESSURE START SYSTEM OPEN VALVES START TURBINE PUMP I

• PUMP WATER TO CORE EXAMPLE kEACTOR VESSEL LOI WATER LEVEL Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Relationship Between Protective Functions and Protective Actions Figure 1-2-2

BWR SAFETY SAFETY SYSTEMS PROTECTIVE ACTIONS SAFETY ACTIONS WER GEN RA ION SYST MS NOTE I N

SAFETY OBJECTIVES NOTE I z

8~

PROCESS POWER z<

PROCESS SAFETY z"'

PROTECTIVE

<w SYSTEM GENERATION

..JO.

ACTION 0.0 SYSTEM PROCESS SAFETY SATISFY ACTION SAFETY PROCESS HJ PROCESS SAFETY ~

PROTECTIVE POWER SYSTEM GENERATION ACTION SYSTEM PROTECTIVE Hi

• ~

POWER ACTION

<o>-

GENERATION SYSTEM SAFETY SATISFY ACTION SAFETY OBJECTIVE PROTECTIVE ~

POWER GENERATION ACTION SYSTEM PROTECTIVE H,

~

POWER ACTION GENERATION SAFETY SATISFY SYSTEM ACTION SAFETY PROTECTIVE ~

OBJECTIVE POWER GENERATION ACTION SYSTEM SPECIAL rH POWER SAFETY GENERATION SYSTEM SPECIAL SATISFY SYSTEM SAFETY SAFETY ACTION OBJECTIVE SPECIAl rH SPECIAL POWER SAFETY SAFETY GENERATION SYSTEM ACTION SYSTEM IAFETY SYSTEMS PROTECTIVE ACTIONS SAFETY ACTIONS SAFETY OBJECTIVES POWER GENERATION SYSTEMS

~OTES i ONLY TWO SYSTEMS OF EACH TYPE ARE SHOWN THERE MAY BE MORE THAN THIS NUMBER OF SYSTEMS IN ANY CATEGORY, THERE MAY BE CASES WHERE !Hf.SYSTEM LEVEL ACTION IS IOENTICAL TO THE ULTIMATE ACTION IN THE PLANT, IN SUCH A CASE THE INTERMEDIATE SYSTEM LEVEL ACTION NEED NOT BE IDENTIFIED.

BWR MISSION

---

~~-

POWER GENERATION ACTIONS ACN10N I I SATISFY POWER POWER GENERATION GENERATION ACTION OBJECTIVE POWER GENERATION SYSTEM ACTION I

IA TISFY POWER POWER GENERATION GENERATION ACTION OBJECTIVE POWER GENERATION SYSTEM ACTION POWER GENERATION SY ITEM ACTION I

POWER SATISFY POWER GENERATION GENERATION POWER ACTION OBJECTIVE GENERATION SYSTEM ACTION POWER GENERATION SYSTEM ACTION I

~

SATISFY POWER POWER GENERATION GENERATION GE~fm10N ACTION OBJECTIVES SYSTEM ACTION POWER GENERATION SYSTEM POWER GENERATION ACTION POWER GENERATION ACT! NS OBJECTIVE!

Nebraska Public Power District COOPER NUCLEAR STATION UPDATED SAFETY ANALYSIS REPORT (USAR)

Relationship Between Different Types of Systems Actions and Objectives Figure 1-2-3

u..

Figure I-5-1 Safety-Related Engineered Safety Design Basis Functions, Features Accidents (LOCA, Structures, RDA, MSLB, FHA)

Systems and Components Protection Systems Safety-Related and Non-Safety-Safety Functions Abnormal Related Nuclear Safety Systems and Systems Operational Functions, Transients Structures, Systems and Components*

Special Safety Systems Special Events Non-Safety Related Process Safety Systems Non Protection Functions, Systems Planned Structures, Operations Systems and Power Generation Power Generation Components Systems Functions and Systems RELATIONSHIP OF VARIOUS CATEGORIES OF SYSTEMS (The same horizontal level of one column relative to another column denotes equivalency)

• Non-safety-related functions and SSCs may be credited in mitigating Abnormal Operating Transients provided the event is enveloped by safety-related functions and SSCs. Assuming the non-safety-related equipment fails, safety-related equipment must ultimately assure: a) the integrity of the Reactor Coolant Pressure Boundary, b) the capability of shutting down the reactor and maintaining it in a safe shutdown condition, and c) the capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10CFRl00 (or 10CFRS0.. 67 for Fuel Handling Accident).

03/09/07