ML19320A252
| ML19320A252 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/13/1972 |
| From: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8004210543 | |
| Download: ML19320A252 (2) | |
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NOV 1 3 1972 Docket No. 50-313 Mr. J. D. Phillips Vice President & Chief Engineer Arkansas Power & L.ght Company Sixth and Pine St2 eats I
Pine Bluff, Arkanaas 71601 i
Dear Mr. Phillips:
As presented in Amendment No. 25 to the FSAR, you have proposed that the Technical Specifications for operation of Arkansas Nuclear One - Unit 1 require periodic surveillance of nine (9) reactor building tendons for symptoms of material deterioration or force reduction. You have proposed surveillance of 3 of the 171 horizontal tendons, 3 of the 102 vertical tendons, and 3 of the 90 dome tendona for the total of nine. The basis for selecting nine surveillance tendons is given as the Bechtel Corp.
document "A Review of the Statistical Significance of Tendon Surveillance."
- In discussions of this matter, your staff has further referred to the American Concrete Institute standard ACI 349 which recommends surveilla of a minimum of 2% of the tendon population which would be at least 7 of the 363 Unit 1 tendons.
It is our position that, in spite of the commonality of tendon parts, installation procedures, etc., a broad surveillance program is needed for at least the early years of plant operation.
The number of tendons involved in such a surveillance program is relatively independent of the exact number of tendons used in the building and is more a function of the geometric and environmental differences found in the various sections of the building.
It is our position, therefore, that the tendon surveil-lance for the reactor building of Unit 1 should include examination of 10 of the 171 horizontal tendons, 5 of the 102 vertical tendons, and 6 of the 90 dome tendons for a total of 21 surveillance tendons in order to provide adequate' assurance that unacceptable matarial deterioration or force reduction does not occur.
l Documentation of this Regulatory position is forthcoming in a formal safety guide on inservice surveillance of tendons.
In addition, this regulatory position is in accordance with Appendix B of the Proposed Standard Code for Concrete Reactor Vessels and Contain-ments (draft dated August 1,1972).
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.Mr. J. D. Phillips NOV 13 1972 The Tech =4em1 Specifications for Unit 1 should be revised to reflect this position.
Sincerely, Stigleal Signed h.
L 8. DeYeast R. C. DeYoung, Assistant Director for Pressurised Water Reactors Directorate of Licensing ces Horsee Jewell, Esquire House. Holms 4 Jewell 1550 Tower b41d4=-
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