NLS8400111, Forwards Pages 2-14 & 2-15 Which Were Inadvertently Omitted from 840305 Rev 1 to Cooper Nuclear Station QA Program

Forwards Pages 2-14 & 2-15 Which Were Inadvertently Omitted from 840305 Rev 1 to Cooper Nuclear Station QA Program

ML20094F650
Person / Time
Site:	Cooper
Issue date:	04/03/1984
From:	Pilant J NEBRASKA PUBLIC POWER DISTRICT
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
NLS8400111, NUDOCS 8408100145
Download: ML20094F650 (3)

Text

-m o

e t GENERAL OFFICE P.O. BOX 499. COLUMBUS, NEBRASKA 68e01-0499 Nebraska Public Power D tn. t is c

mmoNE = sensei

-a.

NLS8400111 April 3, 1984

@Q]h JJ h

APR - 51984 J

Mr. John T. Collins M

Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

Subject:

Omitted Pages from Cooper Nuclear Station Quality Assurance Program Re ference : NPPD Letter, Jay M. Pilant to John T. Collins (NLS8400080) dated March 5, 1984

Dear Mr. Collins:

The referenced letter transmitted the Cooper Nuclear Station Quality Assurance Policy Document, Revision 1.

Attached please find Pages 2-14 and 2-15 (Table 1) which were inadvertently omitted from that document.

Please place them in the appropriate order in Section 2.0

SUMMARY

DESCRIPTION, following Page 2-13.

I apologize for the inconvenience.

Sincerely, Jay M. Pilant Technical Staf f Manager Nuc1 car Power Group

/ bas Attachment cc: NRC Document Control Desk Iy$

56/

gyg8WasMjjg M

lg P

t l

TABLE 1

()

SAFETY-RELATED (ESSENTIAL) SYSTEMS COVERED BY THE QUALITY ASSURANCE PROGRAM I.

Nuclear Steam Supply System a.

Reactor Primary Vessel

=

b.

Reactor Primary. Vessel Supports c.

Control Rods and Drive Systen equipment necessary for Scram Operation d.

Control Rod Drive Housing e.

Fuel Assemblies.

f..

Core Shrodd g.

Steam Dryer h.

Steam Separator II.

Reactor Coolant Systems

.a.

ADS - Automatic Depressurizati'on' System b.

HPCI - High Pressure Coolant Injection System c.

LPCI - Low Pressure Coolant Injection System d.

CS. - Core Spray System e.

RCIC - Reactor Core Isolation Cooling O

III.-Reactor Protection and Engineered Safeguard Systems a.

Reactor Protection System b.

Rod Sequence Control System c.

Standby Liquid Control d.

Standby Gas Treatment e.

Diesel Generators f.

Electrical Aux Power 1.

Critical 4160 V Equipment 2.

Critical 480 V Equipment g.

Neutron Monitoring Systems 1.

APRM 2.

IRM 3.

LPRM 4.

RBM 5.

SRM 6.

TIP h.

DC Power Supply 1.

Nuclear System Leak Detection J.

Containment Isolation System k.

Nuclear Boiler and Related Instrumentation 1.

Primary Cortainment m.

Rod Position Indicator O

2-14 Revision 1

l e'

TABLE 1 (Cont'd) f%

\\.J IV.

Nuclear Fuel Systems a.

Refueling Interlocks for Fuel Handling and Vessel Servicing Equipment b.

Fuel Pool Liner and Gates c.

Fuel Pool Cooling and Cleanup V.

Radioactive Waste Disposal Systems a.

Process Radiation Monitoring System 1.

Off-Cas Vent Pipe Radiation Monitoring 2.

Off-Cas Monitoring 3.

Aug Off-Cas Monitoring 4.

Main Steam Line Monitoring 5.

Reactor Building Vent Monitoring (CE) 6.

Drywell and Suppression System Leak Rate 7.

Liquid Process Radiation Monitoring VI.

Other Essential Support Systems a.

Reactor. Equipment Cooling f-~g b.

Service Water 5,,_)

c.

Emergency Bypass Function on Control Room Heating, Vent, and AC d.

Reactor Recirculating (Pressure Retaining Parts Only) e.

Class I, II, and III Code Items f.

Reactor Feed Pumps (Pressure Retaining Parts Only) g.

Reactor Building H&V VII. Structures (Seismics) a.

Reactor Building b.

Control Building c.

Elevated Release Point d.

Intake Structure e.

Diesel Cencrator Building f.

Radwaste Building (Below Grade) l l

NOTE:

Even though a system is classified as ESSENTIAL, each individual component within that system may or may not be Essential.

2-15 Revision 1