ML19345A394

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Safety Evaluation Supporting Proposed Change 77 to Tech Specs
ML19345A394
Person / Time
Site: Yankee Rowe
Issue date: 10/29/1966
From: Boyd R
US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML19345A392 List:
References
NUDOCS 8011210286
Download: ML19345A394 (2)


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SAFETY EVALUATION BY ' hie RESEARCH AND POWER REACTOR SAFETY BRANCH DIVISION OF REACTOR LICENSING IN THE MATTER OF YANKEE ATOKIC ELECTRIC COMPANY PROPOSED CHANGE NO. 77 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. 77, dated October 20, 1966, requested authorization to change the Technical Specifications attached as Appendix A to License No. DPR-3.

The proposed change would authorize reactor operation with a reduction from 27 to 14 in the number of available core thermocouples. This change was requested because some of the thermo-couples may have been damaged during the current shutdown to load Core VI, and their operability will not be determined until the refueling operation has been completed.

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Discussion

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The radial power distribution in the Yankee core is monitored by the core l

thermocouples and the flux wire system. This information is required to determine the relative power output of the fuel assemblies. These measure-ments during previous cores have verified that the analytical predictions of the core power distribution are accurate indications oft actual operating conditions. Yankee has reported that some of the core thermocouples may not be operable during Core VI.

However, because of the symmetrical fuel loading pattern and the large safety margins predicted for the Yankee core, ample monitoring will still be provided by the 14 remaining thermocouples and the 20 flux wires. In addition, since the reactor power level is controlled primarily by chemical shim and not by control rod motion, a

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machanism does not exist to induce large changes in the reactor power distribution. Therefore, we believe that reactor operation with the 14 available core thermocouples is satisfactory.

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8011210286

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Con lasion We have concluded that the proposed change does not present significant hazards considerations not described or isolicit in the hazards aummarv report, and that there is reasonable assurance that the health and safety of the public will not be endangered.

Original signed by:

Re-cr S %d Roger S. Boyd, Chief Research & Power Reactor Safety Branch Tivision of Reactor Licensing Date: OCT 2 91966 l

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