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

{{Adams
| number = ML20094F650
| issue date = 04/03/1984
| title = Forwards Pages 2-14 & 2-15 Which Were Inadvertently Omitted from 840305 Rev 1 to Cooper Nuclear Station QA Program
| author name = Pilant J
| author affiliation = NEBRASKA PUBLIC POWER DISTRICT
| addressee name = Collins J
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION IV)
| docket = 05000298
| license number = 
| contact person = 
| document report number = NLS8400111, NUDOCS 8408100145
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
}}

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    -                                                                         GENERAL OFFICE P.O. BOX 499. COLUMBUS, NEBRASKA 68e01-0499 Nebraska Public Power Dis tn.c t                         mmoNE = sensei
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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$ gyg8WasMjjg                                                                 M 56/
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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

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* 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}}