ML20082T199
| ML20082T199 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 12/09/1983 |
| 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.3, TASK-2.D.3, TASK-2.E.1.1, TASK-2.F.1, TASK-2.F.2, TASK-TM 662, GL-83-37, NUDOCS 8312150230 | |
| Download: ML20082T199 (2) | |
Text
d; VIRGINIA ELECTRIC AND PowEn COMPANY Rrcirwown,VinorxrA 20c61 W. L. Srmwsar Vaca Pasesnawr December 9, 1983 NUCI.EAM Oramarrows Mr. Harold R. Denton, Director Serial No. 662 Office of Nuclear Reactor Regulation N0/JDH:acm Attn:
Mr. Darrell G. Eisenhut, Director Docket Nos. 50-280 Division of Licensing 50-281 U. S. Nuclear Regulatory Commission 50-338 Washington, D. C. 20555 50-339 License Nos. DPR-32 Gentlemen:
DPR-37 NPF-4 NPF-7 VIRGIMIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNITS 1 AND 2 SURRY POWER STATION, UNITS 1 AND 2 GENERIC LETTER 83-37, NUREG-0737 TECHNICAL SPECIFICATIONS This letter is provided in response to a request by the North Anna Project Manager regarding the status of our response to Generic Letter 83-37.
Generic Letter 83-37, NUREG-0737 Technical Specifications, dated November 1, 1983, requested licensees to submit Technical Specifications for reactor coolant system vents (NUREG 0737 Item II.B.1) within 30 days of receipt of the letter, and submit specifications for ten other NUREG-0737 items specified in the letter within 90 days.
Proposed Technical Specifications for the reactor coolant system vents for both North Anna and Surry were submitted to NRC by letters dated June 9, 1983 (North Anna; Serial No. 333A) and June 16, 1983 (Surry; Serial No. 330).
In addition. Technical Specifications have already been submitted for six of the ten remaining items:
Noble Gas Effluent Monitors (II.F.1.1), Containment Hi-Range Radiation Monitor (II.F.1.3),
Containment Pressure Monitor (II.F.1.4), Containment Hydrogen Monitor (II.F.1.6), and Instrumentation for Detection of Inadequate Core Cooling (II.F.2).
We are currently reviewing the four remaining items:
Post-Accident Sampling System (II.B.3), Long Term Auxiliary Feedwater Systems Evaluation (II.E.1.1),
Sampling and Analysis of Plant Effluents (II.F.1.2),
and Control Room Habite.bility Requirements (II.D.3.4).
For these four items, we intend to submit proposed Technical Specifications, if appropriate, in <ccordance with the schedule ;pecified in the generic letter.
V h truly.yours, U.
p W. L. Stewart 8312150230 831209 PDR ADOCK 05000280 P
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NRC Resident Inspector-Surry Power Station Mr. M.~B.~Shymlock NRC Resident Inspector
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