ML19309A056
| ML19309A056 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/04/1970 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19309A057 | List: |
| References | |
| NUDOCS 8003240891 | |
| Download: ML19309A056 (3) | |
Text
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Design of Tendon Anchorage Zones".
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March 4, 1970 The Director Division of Reactor Licensing United States Atomic Energy Commission Washington, D. C. 20545
Dear Sir:
In re: Florida Power Corporation Crystal River Nuclear Generating Plant Docket No. 50-302 Enclosed are three (3) executed originals and nineteen (19) conformed copies of Amendment No. 8, consisting of Supplement Nos. 5 and 6 to the Preliminary Safety Analysis Report for our Crystal River Nuclear Generating Plant Unit 3.
Also enclosed are an additional eighty-one (81) copies of each for updating the balance of the copies of the Preliminary Safety Analysis Report filed with the original Ap-plication.
Amendment No. 8 supplements the Preliminary Safety Analysis Report so as to include the latest design information for your contin-uing review.
Supplement No. 5 includes The Prescon Corporation's presenta-tion on " Tests on 1170 Ton Prescon Tendons." -Supplement No. 6 consists of supplemental data on the " Analysis and Design of Tendon Anchorage Zones."
The tests as reported in Supplement 5 of the PSAR are consi-dered to be valid in demonstrating that the components as sized and made from steel with Fy equal to or greater than 50,000 psi and Fu equal to or greater than 90,000 psi can safely transmit the tendon force to the structure.
During a low temperature test one of the four dead end plates tested developed a surface crack but continued to carry required test load during subsequent tests. An examination of the plate was performed by Metallurgical Consultants of Houston (results included in Supplement 5) to establish the causes of the crack. Their report notes that the primary causes of the crack were the detrimental effects of flame cutting and the large differences in grain structure through-l out the plate.
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The Director Division of Reactor Licensing March 4, 1970 The low temperature tests on the full size components indica-ted that AISI C1045HR steel as fabricated may have questionable behavior at low temperatures. AISI C1045 (fine grain practice) with more exacting control during fabrication and subsequent normalizing is considered to have satisfactory low temperature performance. However, the requirements of construction are such that possible additional low temperature testing could not be completed without costly construction delays. Based upon the schedule requirements the steel selected for the anchorage components will be a steel meeting the criteria stated below. The low temperature perfor-mance of the alternative steel will be assured by meeting this criteria, even though the actual manner and loading of the components precludes severe impact loads.
The material to be incorporated into the anchorage component hardware will meet the following criteria:
(1)
Fy = 50,000 psi min.
(2)
Fu = 90,000 psi min.
(3) NDTT = -lS*F or acceptable impact test requirements at this temperature.
(4) Hardness will be compatible with buttonhead test performance requirements.
Construction of the tendon anchorage zone area in the mat, is scheduled to begin in April,1970. Construction of the anchorage zone in the Reactor Building cylinder is scheduled to begin in September,1970.
Design details of the anchorage in these areas are provided. This supple-mental information is in response to your letter dated November 8, 1969.
Very truly yours,
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J. "T. Rodgers' Nuclear Project Manager JTR/sc Enclosures.
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