ML19347C500
| ML19347C500 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/14/1962 |
| From: | Bryan R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19347C499 | List: |
| References | |
| NUDOCS 8011190775 | |
| Download: ML19347C500 (1) | |
Text
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0 HAZARDS ANALYSIS BY THE RESEARCH AND POWER REACTOR SAFE'IY BRANCH DIVISION OF LICENSING AND REGULATION IN THE MATTER OF YANKEE ATOMIC ELECTRIC COMPANY PROPOSED CHANGE NO. 22 DOCKET NO. 50-29
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Iatroduction Pursuant to the provisions of paragraph 3.A. of License No. DPR-3, as p "l:
amended, Yankee Atomic Electric Company in Proposed Change No. 22, e
dated April 18, 1962, requested authorization to install a three-quarter
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inch stainless steel isolation valve and tee connection in the pressure F ~
equalizing line between the prinary system safety valve discharge header and the low pressure surge tank. A capped line and valve would be in-sc;.
stalled on the tee connection.
This piping modification would provide J=~
a means of purging hydrogen gas from the safety valve discharge header
!7 without the necessity of also purging the low pressure surge tank at the p:==
same time. Such an arrangement would facilitate primary system safety valve maintenance.
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Discussion Yankee has indicated that the valves and piping to be ased in making the proposed connecticns will be designed, fabricated and tested in accordance with the American Standards Association Code fo~r Pressure Piping. The valves will normally be set so that they will not alter the present operat-ing conditions. Further,use of the valves to isolate the hydrogen atmosphere of the low pressure surge tank during reactor operation would not have a significant effect on the ability of the system to function properly.
In view of the above, there appears to be' adequate assurance that~the proposed o
modifications will be properly designed and installed and that their presence in the system will not have an adverse effect on the safety of operation.
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Conclusion Based on our review of the proposed change, we have concluded that it does not present significant hazards considerations not described or-implicit in the license application as amended to June 23, 1961. We have further con.
cluded that there is reasonable assurance that.the health and safety of the public will not be endangered by operation of the facility as proposed.
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l Origina!tigned
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by hhrt H. Bryan Robert H. Bryan, Chief Research & Power. Reactor Safety Branch 8 011 p g) 26~'
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nc 14 E2 Date:
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