ML21130A062

0 to Updated Final Safety Analysis Report,Section I, Figures

ML21130A062
Person / Time
Site:	Cooper
Issue date:	04/21/2021
From:	Nebraska Public Power District (NPPD)
To:	Office of Nuclear Reactor Regulation
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References
NLS2021013
Download: ML21130A062 (5)

Text

Legend

1. = Flow, lbm/hr 1020 ',,\

H = Enthalpy, Btu/lbm p "

F = Temperature, °F M = Moisture, % Main Steam Flow 9.707E+o6 #

• P = Pressure, psia 1191.5 H

• 0.39 M

• Carryunder = 0.22% 968 P

• 2419 Main Feed Flow MWt Wd= 100 % ,$.772E+o6 # 9.672E+o6 #

520.5 H 341.8 H 341.1 H 527.2 Of Total 367.7 °F 367.1 °F Core Flow 73.5E+06

~h =0.7 H J,tl l.000E+05 #

407.6 H 429.2 °F Cleanup Demineralizer System 3.500E+-04 # Control Rod Drive I.000E+05 #

68.0 H Feed Flow 519.8 H 97.2 °F 526.6 °F

• Conditions at upstream side ofTSV Core Thennal Power 2419.0 Pump Heating 7.4 Cleanup Losses -3.3 Other Szstem Losses -0.6 Turbine Cycle Use 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

rs"AFErv-,

I SYSTEM B I I I L. _J r---, ,-----,

I I SAFETY I PROTECTIVE SAFETY I L ___ --'I I ___ J smEIIA I ACTION B I SYSTEM C L

1 PROTECTIVE PROTECTIVE ACTION A ACTION C SAFETY ACTION -

CONCEPT

,-;;D-;-,

I A-C I I POWER I L.J!r..J r---,

I CORE I PROVIDE A-C POIER I SPRAY I L~ST~_J 1

PUMPIATER PUIIPIATER TO CORE TO CORE CORE STBY.

COOLING (LOI PRESSURE)

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

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

SAFETY SYSTEM PROTECTIVE PROTECTIVE FUNCTION A FUNCTION B INTRA-SYSTEM ACTIONS PROTECTIVE ACTION CONCEPT HIGH PRESSURE COOLANT INJECTION SYSTEM HIGH kEACTOR DRYIELL VESSEL LOI PRESSURE WATER LEVEL START SYSTEM

- OPEN VALVES START TURBINE PUMP I

PUMP WATER TO CORE EXAMPLE 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 BWR MISSION

---

~~-

SAFETY SYSTEMS PROTECTIVE ACTIONS WER GEN RA ION SYST MS POWER GENERATION ACTIONS NOTE I N SAFETY ACTIONS SAFETY OBJECTIVES NOTE I z

8~

z< PROCESS POWER z"'

PROCESS SAFETY

<w PROTECTIVE GENERATION SYSTEM I

..JO.

ACTION I

0.0 SYSTEM ACN10N SATISFY PROCESS SAFETY SATISFY POWER POWER ACTION GENERATION GENERATION SAFETY OBJECTIVE HJ ACTION PROCESS SAFETY ~ PROCESS POWER POWER PROTECTIVE GENERATION SYSTEM ACTION GENERATION SYSTEM SYSTEM ACTION Hi

• ~

PROTECTIVE POWER ACTION <o>- GENERATION SYSTEM IA TISFY I

SAFETY SATISFY POWER POWER ACTION SAFETY GENERATION GENERATION OBJECTIVE ACTION OBJECTIVE POWER POWER PROTECTIVE GENERATION ACTION ~ GENERATION SYSTEM SYSTEM ACTION PROTECTIVE H, POWER POWER

~

GENERATION GENERATION ACTION SY ITEM SATISFY SYSTEM ACTION POWER SATISFY I

SAFETY POWER ACTION SAFETY GENERATION GENERATION OBJECTIVE POWER ACTION OBJECTIVE PROTECTIVE POWER

~

GENERATION GENERATION SYSTEM ACTION SYSTEM ACTION rH SPECIAL POWER POWER GENERATION GENERATION SAFETY SYSTEM SYSTEM SYSTEM ACTION SATISFY I

SPECIAL SATISFY

~

POWER POWER SAFETY SAFETY GENERATION GENERATION rH ACTION OBJECTIVE ACTION OBJECTIVES SPECIAl SPECIAL POWER GENERATION GE~fm10N SAFETY SAFETY SYSTEM SYSTEM ACTION SYSTEM ACTION POWER GENERATION SYSTEMS POWER GENERATION SYSTEM POWER GENERATION ACTION POWER GENERATION IAFETY SYSTEMS PROTECTIVE ACTIONS SAFETY ACTIONS SAFETY OBJECTIVES OBJECTIVE!

ACT! NS

~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.

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 Design Basis Functions, Engineered Safety Accidents (LOCA, Structures, Features 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 Structures, Planned Systems and Operations 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