ML20140J417

Forwards Proposed Change 5 to TS Re Limit on Reactor Primary Sodium Temp heat-up & cool-down Rates to Provide Assurance That Reactor Vessel Head Bolt Stresses Remain Below ASME Allowable Values

ML20140J417
Person / Time
Site:	05000231
Issue date:	04/28/1971
From:	Cohen K US ATOMIC ENERGY COMMISSION (AEC)
To:	Morris P GENERAL ELECTRIC CO.
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References
FOIA-97-34 NUDOCS 9705140073
Download: ML20140J417 (2)

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GENERAL ELECTRIC C0tiPANY t

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.mt DocketgNo. 50-231 D

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License DR-15 APR 2s Bh 2e a

CD Dr. Peter A. Morris, Director Regulatory File Cy.

Division of Reactor Licensing U. S. Atomic Energy Commission Washington, D. C.

20545

Dear Sir:

The attached Proposed Change No. S to the Technical Specificatiens is submitted in partial response to the request for additional information contained in your letter of April 19, 1971.

Information on the remaining items outlined in your letter was discussed in a meeting with members of your staff on April 27, 1971, and will be documented in the necr future.

The attached proposed specifications include limits on reactor primary sodium temperature heat-up and cool-down rates to provide assurance that the reactor vessel head bolt stresses remain below the ASME code allow-able values.

In addition, it defines an in-service inspection program to verify the adequacy of the proposed limita.

Very truly yours, k' 9 M

& St &L Karl Cohen, General Manager Nuclear Energy Division Sunnyvale, California 94806 N

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USAEC H:

,wR 281971 * :5 REGULATORY 9066 Q

MAIL SECTION DOCKET CLERK 6

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Introduction

• gin accordance with the provisions of 10 CFR 50, General Electric requests that the SEFOR Technical Specifications be amended by adding paragraphs l

3.4.L. 3.4.M. 3.4.N. 3.4.0, 4.4.R and 4.4.S, and the bases for these paragraphs, as given in Appendix I of this document.

II.

Discussion Analyses of the stress levels in the reactor vessel head bolts have indicated that the bolt stress levels will remain below the ASME code values when the temperature tranaient limits and pre-load limits proposed in the attached changes to the Technical Specifications are observed. The analyses were discussed with members of the DRL staff at a meeting in Bethesda on April 27, 1971.

Documentation of this information is being prepared and will be submitted to DRL in the near future.

Surveillance requirements are included in the proposed specifications to provide assurance that operation of the reactor within the proposed limits does not result in damage to the outer head bolts. The first of the periodic examinations required by *he proposed surveillance program will be performed on or before August 31, 1972. In addition, one of the three reactor vessel outer head bolts removed for inspection during March 1971 will be removed and examined for evidence of permanent elongation following the Core I sub-prompt testing and prior to Core I super-prompt testing.

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