ML19345A618
| ML19345A618 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/23/1963 |
| From: | Bryan R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19345A615 | List: |
| References | |
| NUDOCS 8011240339 | |
| Download: ML19345A618 (2) | |
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IIAZARDS ANALYSIS BY T11E RESEAROI AND POWER REACTOR SAFETY BRANCH DIVISION OF LICENSING AND REGULATION
,.W IN THE MATTER OF YANKEE ATOMIC ELECTRIC COMPANY R
PROPOSED OIANGE NO. 30 DOCKET NO. 50-29 Introduction Pursuant to the provisions of paragraph 3. A of License No. DPR-3, as amended. Yankee Atomic Electric Company in Proposed Change No. 30, dated November 6,1962, requested authorization to revise the last sentence of paragraph D.2.e.(7) of the Technical Specifications attached as Appendix "A" to the license.
This request was made by Yankee for the purpose of making the Technical Specifications consistent with the re-a:
quirements of the Operating Instructions which are incorporated by
^': jus reference into the Technical Specifications.
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Discussion
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Paragraph D. 2.e.(7) of the Technical Specifications now reads as follows:
"The automatic controls associated with the reactor protection
~ ~r system will be maintained at the set points listed in Table I, attached hereto, or at set points representing more conserva-tive values of the particular variables being measured. Table I also shows the number of channels associated with each function and the number of channels normally required to initiate a scram signal.
In the event of failure of one instrument channel when multiple channel protection 'is provided for a function, the plant will continue regular operation.
The scram circuits, however, will then operate so that activation of any of the remaining channels for that function will cause scram operation."
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The Change which Yankee has proposed would revise the last sentence of the paragraph to read:
g "The scram circuits, however, will then operate so that activation of any of. the remaining channels for that - func-tion will cause scram operation, except as provided in the authorization of Change No. 23."
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. We had previously considered the instrumentation coincidence scram re-quirements provided by Change No. 23 and concluded at that time that they were adequate and did not present significant hazards considera-tions not described or implicit in the license application as amended to June 23, 1962. We have now further reviewed these requirements and
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find no reason to change our previous judgement regarding these coinci-dence requirements.
Conclusion In view of the foregoing, we have concluded that Proposed Change No. 30 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.
Ori;inal:! ped by Ebert H. Bryu Robert H. Bryan, Chief
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Research & Power Reactor Safety Branch Division of Licensing and Regulation Date JAN 2 41933 m
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