ML18139C241
| ML18139C241 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/14/1983 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139C240 | List: |
| References | |
| NUDOCS 8302180448 | |
| Download: ML18139C241 (5) | |
Text
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e ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE
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Section 3.15 3.16 3.17 3.18 3.19 3.20 3.21 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 4.10 4.11 4.12 4.13 4.14 4015 4.16 4.17 4.18 4.19 Title Containment Vacuum System Emergency Power System Loop Stop Valve Operation Movable Incore Instrumentation Main Control Room Ventilation System Shock Suppressors (Snubbers)
Fire Detection and Suppression System SURVEILLANCE REQUIREMENTS Operational Safety Review Reactor Coolant System Component Inspections Reactor Coolant System Integrity Testing Following Opening Containment Tests Spray Systems Tests Emergency Power System Periodic Testing Main Steam Line Trip Valves Auxiliary Feedwater System Effluent Sampling and Radiation Monitoring System Reactivity Anomalies Safety Injection System Tests Ventilation Filter Tests Deleted.
Deleted Augmented Inservice Inspection Program for High Energy Lines Outside of Containment Leakage Testing of Miscellaneous Radioactive Materials Shock Suppressors (Snubbers)
Fire Detection and Protection System Surveillance Steam Generator Inservice Inspection ii TS ii TS 3.15-1 TS 3.16-1 TS 3.17-1 TS 3.18-1 TS 3.19-1 TS 3.20-1 TS 3.21-1 TS 4.0-1 TS 4.1-1 TS 4.2-1 TS 4.3-1 TS 4.4-1 TS 4.5-1 TS 4.6-1 TS 4.7-1 TS 4.8-1 TS 4.9-1 TS 4.10-1 TS 4.11-1 TS 4.12-1 TS 4.15-1 TS 4.16-1 TS 4;17-1 TS 4.18-1 TS 4.19-1
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continuous exposure to the concentration values listed in Appendix B, Table II of 10 CFR 20, estimates of the likely resultant exposure to individuals and to population groups, and assumptions upon which estimates are based shall be provided.
(3)
If a particular sample or measurements indicate statis-tically significant levels of radioactivity above established or concurrent backgrounds, the following information shall be provided:
(a)
The type of analysis performed; e.g., alpha, beta, gamma and/or isotopic.
(b)
The minimum sensitivity of the monitoring system.
(c)
The measured radiation level or sample concentration.
(d)
The specific times when samples were taken and measurements were made.
(e)
An estimate of the likely resultant exposure to the public if it exceeds 10 mrem.
TS 6.6-14
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e ATTACHMENT 2 DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGE
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e DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGE This proposed change deletes the non-radiological water quality Technical Specifications 4.13, 4.14, and 6.6.3.d.
This change is an administrative action at the request of the NRC.
The water quality limits and monitoring program are now under the jurisdiction of the U. S. Environmental Protection Agency as established by the Federal Water Pollution Control Act Amendment of 1972.