ML20072S912
| ML20072S912 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/31/1983 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.B.2, TASK-2.F.1, TASK-2.F.2, TASK-TM 713B, NUDOCS 8304070386 | |
| Download: ML20072S912 (1) | |
Text
VINGINIA ELECTRIC AND PowEn COMPANY RIcuxoNn,VIROINIA 23261 W.L. STEWART Vice Pa==tomwr weci.=in or= =ino==
March 31, 1983
'Mr. Harold R. Denton, Director Serial No. 713B Office of Nuclear Reactor Regulation N0/JHL:acm Attn:
Mr. Darrell G. Eisenhut, Director Docket Nos. 50-338 Division of Licensing 50-339 U. S. Nuclear Regulatory Commission License Nos. NPF-4 Washington, D. C. 20555 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 EXCEPTIONS TO TECHNICAL SPECIFICATION REQUIREMENTS OF NUREG-0737 In our letter dated December 28, 1982 (Serial No. 713), Vepco stated that Technical Specifications pertinent to NUREG-0737 items / systems will be submitted by April 1, 1983.
Vepco has contracted with the architectural engineer of the systems to supply the Technical Specifications for the NUREG-0737 items / systems. There has been a significant - delay in receiving these Technical Specifications from the architectural engine.cr, therefore, the Technical Specifications cannot be submitted.
Vepco will submit the Technical Specifications pertinent to the following NUREG-0737 items / systems by June 1, 1983, Items: II.F.1.1-Noble Gas Effluent
- Monitors, II.F.1.3-Containment High Range Radiation
- Monitors, II.F.1.4-Containment Pressure Monitors, II.F.1.5-Containment Water Level
- Monitors, II.F.1.6-Containment Hydrogen Monitors, II.B.1-Reactor Coolant System Vents and II.F.2-Installation of Instrumentation for Detection of Inadequate Core Cooling. -The Reactor Coolant System Vents (Item II.B.2) are installed and require post-implementation review but they are dependent on the NRC Staff approval of the Reactor Vessel Level Indication System (Item II.F.2). The Reactor Vessel Level Indication System (Item II.F.2) has been installed and calibrated but it also requires a post-implementation review by the NRC Staff.
Very truly yours, D
MM IIB 304O'70386"030331 W. L. Stewart PDR-ADOCK 05000338 P
PDR cc:
Mr. Robert A. Clark, Chief Operating Reactor Branch No. 3 Division of Licensing l
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