ML19351D740
| ML19351D740 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/13/1965 |
| From: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19351D739 | List: |
| References | |
| NUDOCS 8011170773 | |
| Download: ML19351D740 (1) | |
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UNIT 2D STATES ATOMIC ENERGY COMMISSION SAFETY EVALUATION BY THE RESEARCH AND POWER REAC"OR SAFETY BRANCH DIVISION OF REACTOR LICENSING IN THE MATTER OF YANKEE ATOMIC ELECTRIC COMPANY PROPOSED CHANGE NO. 66 DOCKET NO. 50-29 Introduction Pursuant to the provisions of Section 50.59 of the Commission's regulations.
Yankee Atomic Electric Company in Proposed Change No. 66, dated July,29,1965, requested authorization of a change in the Technical Specifications attached as Appendix A to License No. DPR-3.
This proposed change would authorize installation of:
(1) a primary coolant sample line, motor operated valve, and sample return line to the low pressure surge tank, and (2) a flowmeter in the discharge line from the low pressure surge tank make-up pumps.
Discussion Yankee is conducting a continuing program to determine the chemical and radiolytic composition of the primary coolant system. To aid in these evalua-tions, sevaral modifications to the Charging and Volume Control System have been proposed. These modifications would provide a primary coolant sample line, upstream of the feed and bleed heat exchangers, that is significantly closer to the reactor than the existing sample line (located near the low pressure surge t ank). Also, a floumeter will be installed in the discharge line from the low pressure surge tank make-up pumps to enable a more accurate assessment of potential leakage from the reactor system. These changes will provide additional information about the primary coolant system, but will not directly affect the operation of the reactor. Therefore, we have concluded that the modifications proposed are desirable additions to the Charging and Volume Control System and should not result in any decrease in the safety of operation.
Conclusion We have concluded that the Proposed Change does not present significant hazards considerations not described or implicit in the hazards summary report, and that there is reasonable assurance that the health and safety of the public will not be endangered.
- /C C d&yr Roger S. Boyd, Chief Research & Power Reactor Safety Branch Division of Reactor Licensing Date:
AUG 13 GS5 8011170773
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