ML18139C190
| ML18139C190 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 12/28/1982 |
| 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.B.3, TASK-2.F.1, TASK-2.F.2, TASK-TM 713, NUDOCS 8301040358 | |
| Download: ML18139C190 (2) | |
Text
e e
VIRGINIA ELECTRIC AND P.QWER COMPANY RICHMOND, VIRGINIA 23261
- w. L. STEWAR:c' VICE PRESIDENT NUCLEAR 0PEB.A.TXONS December 28, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY Serial No. 713 NO/JHL:acm Docket Nos.
50-280 50-281 50-338 50-339 DPR-32 DPR-37 NPF-4 NPF-7 License Nos.
EXCEPTIONS TO TECHNICAL SPECIFICATION REQUIREMENTS OF NUREG-0737 Vepco will submit the Technical Specifications pertinent to the following NUREG-0737 items/systems by April 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 Monitor and II.F.1.6 -
Containemnt Hydrogen Monitors.
In addition, Technical Specifications for Items II.B.l -
Reactor Coolant System Vents and II.F.2 -
Installation of Instrumentation for Detection of Inadequate Core Cooling will be submitted by April 1, 1983.
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.
The Reactor Coolant System Vents (Item II. B. 2) are also installed and they also require post-implementation review but they are dependent on the NRC Staff approval of the Reactor Vessel Level Indication System (Item II.F.2).
Vepco will prepare Technical Specifications for the above systems using the guidance of the existing Technical Specifications for similar and/or related systems or sample Technical Specifications if available.
Currently, NUREG-0737 states that Technical Specifications will be required for Items II.B.3 - Post-Accident Sampling and II.F.1.2 - Sampling and Analysis of Plant Effluents.
A review of 10 CFR 50.36(B)(2) has been performed and it states that, "a limiting condition for operation is the lowest functional capability or performance level of equipment required for the safe operation~
of the facility."
With this definition it has been determined that NUREG-0737, Items II.B.3 - Post-Accident Sampling and II.F.1.2 -
Sampling and Analysis of Plant Effluents do not require Technical Specification changes.
These systems are not used in conjunction with the safe operation of the facility nor do they provide operator guidance in the event of an accident.
These systems are only used for information purposes in the event of an accident.
~: 830t'040358-821228 **-...... -*~**,**,:
- PDR ADOCK 05000280 p
~R I
e VIRGINIA ELECTRIC AND POWER COMPANY TO Harold R. Denton If there are any questions regarding this information, please contact this office.
cc:
Mr. Steven A. Varga, Chief Operating Reactor Branch No. 1 Division of Licensing Mr. Robert A. Clark, Chief Operating Reactor Branch No. 3 Division of Licensing Very truly yours, OL.~
W. L. Stewart