NLS8400111, 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) | |
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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
- 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
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