ML19208C682
| ML19208C682 | |
| Person / Time | |
|---|---|
| Issue date: | 07/25/1979 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Anderson T WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| REF-GTECI-A-11, REF-GTECI-RV, TASK-A-11, TASK-OR NUDOCS 7909270225 | |
| Download: ML19208C682 (4) | |
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'o UNITE D STATES
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NUCLEAR REGULATORY COMMISSION o
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WASM NGTON, D. C. 20556
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JUL 2 5197g Mr. Thomas M. Anderson, Manager Nuclear Safety Department Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230
Dear Mr. Anderson:
SUBJECT:
REVIEW 0F WCAP-9292 Additional information is needed to complete our review of Westinghouse Electric Corporation topical report WCAP-9292 entitled " Dynamic Fracture Toughness of ASME SA 508 Class 2a ASME SA533 Grade A Class 2 Base and Heat Affected Zone Material and Applicable Weld Metals." The additional.
infomation requested is enclosed.
This additional infomation is needed by September 15, 1979 to meet our review schedule.
If you cannot meet this date, please inform us within ten days after receipt of this letter of the date you plan to submit your response.
Sincerely, L
o'n F. Stolz, Ch/ f ight Water Reactors Branch No.1 Division of Project Management
Enclosure:
Request for Additional Information cc: Mr. D. Rawlins Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230
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ENCLOSURE I'
REQUEST FOR ADDITIONAL INFORMATION 120-1 120.0 MATERIALS ENGINEER:NG BRANCH 120.1 In the cover 'ietter attached to Westinghouse Topical Report WCAP-9292 (letter C. Eicheidinger to J. F. Stolz, NS-CE-1730, dated March 17,1978) it is stated that this report was submit-ted in support of nine licensing applications, as'well as any future plants, using SA 508 Class 2a or SA 533 Grade A Class 2 steels in a pressure retaining ccmponent of the reactor coolant pressure boundary. Expand this list of plants to include (a) all operating plants, all plants currently under licensin review (CP or OL), and all standard NSSS designs (PDA or FDA)g (b) the affected compenents, and (c) the specific location in the component (e.g., main coolant RV outlet no::le, RV head flange, pressuri:er maaway) where the subject high strength steels have been, or will be, used.
120.2 (a) Present the details of typical material histories for the subject steels. The hit
- aries should include the as received metallurgical condition and all significant fabrication steps (e.g., type and degree o' working, heat treat:nent time and temperature, welding process description, final product dimensions). Confirm that the steels will be used in the above stated conditions in all applications.
If there are exceptions, indicate what the excepticns are and what operating plants or plants under construction are affected.
(b) Present the details of the test specimen history for the subject steels. The histor/ should include specimen origin (material, form, size and metallurgical condition), location and orientation of the specinens in the original product, degree of working, and heat creatment time and temperature.
120.3 Paragraph G-2110(b), Appendix G of Section III of the ASME Code, states that if materials with a minimum specified yield strength greater than 50 KSI are to be used in conditions where radiation may affect the material properties, the effect of radiation on the X curve shall be determined prior to the use of these materbls in manuf acture. The topical recort presents no data on the effect of radiation on either SA 508 Class 2a or SA 533 Grade A Class 2 materials.
Paragraph IV.S of 10 CFR Part 50, Appendix G, requires that reactor vessel beltline materials have a minimum upper-shelf energy, as determined from Charpy V-notch tests on unirradiated specimens, of 75 ft-lbs unless it can be demonstrated, by appropriate data and analyses, that bwer values of upper-shelf energy still provide adequate margin for deterioration from irrtdiation.
Fran a review of the Charpy I-notch impact energy curves presented in the topical report for the subject steels,
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120-2 it has been determined that the initial upper-shelf energy of SA 508 Class 2a material will be in the range of 60-65 ft-lbs.
Also, no data or analyses were presented in the topical report to justify the use of thie low upper-shelf material in the reactor vessel beltline region.
It is our position that SA 508 Class 2a and SA 533 Grade A Class 2 materials not be used in the beltline region of any reactor vessel until sufficient data are provided for these materials to demonstrate (1) the effect of neutron irradiation on the material properties and (2) compliance with the minimum upper-shelf requirements of Paragraph IV.B of 10 CFR Part 50, Appendix G.
120.4 (a) In Section 4-A of the report it is stated that at low temperatures (below the transition temperature) the material fracture toughness was calculated directly from the failure load, as outlined in ASTM E 399-74. However, it is also stated that in some cases the specified size criterion was not met by the one inch thick CT specimens.
Identify all of the test results that did not meet the E 399-74 size criterion.
(b) For all other tests (those conducted above the transition temperature) identify the criterion that was used to deternine the validity of the test and provide technical justification for using this criterion.
Identify all of the test results that did not meet this criterion.
Prtvide technical justification for the inclusion of any results in this report that did not meet the test validity criteria.
120.5 In order that we may verify the test results of this report, supply the load versus displacement curves for the following tests:
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Material 7;'-Material /TO-Weld festernse 5-1 508-2a 5389 75'F 5-2 508-2a HAZ 5389/4109 25 6-1 533-2 2864 50 6-2 533-2 HAZ' 4336/4113 25 6-2 533-2 Weld 4335/4098 125 Also provide a sample calculation of the J and K values for one of these tests.
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120-3 120.6 Paragraph G-2110(b) Appendix G Section III of the ASME Code states that the K curve may be used for steels having a minimum specified yield strekhth greater than 50 ksi, but less than or equal to 90 ksi, if fracture mechanics data similar to the K data of WRCB-175 are obtained for this material and if all of thfDdata fall above the K
curve. This topical report utilized linear elastic K tests at g
rD low temperatures and J-integral R-curve tests at the uppet transition region and upper-shelf region temperatures to evaluate the dynamic fracture toughness of SA 533 Grade A Class 2 and SA 508 Cla,ss 2a steels and demonstrate comoliance with the code requirement.
The results of the J-integral R-curve testing indicate that, in the upper transit on and upper-shelf temperature regions, SA 533 Grade A However,thesdbe(andtherefore,Ktypetestscondukke and Class 2 steel has an adequate value of J T (the tearing modulus).
SA 508 Class 2a steel were at temperatures relatively low in the transition region and consecuently the data indicate that this material has comparatively low values of J and T as compared to ID SA 533 Class 1 or 2 steels.
To demonstrate the adequacy of SA 508 Class 2a steel in tne upper transition region and upper-shelf region, the topical report should be modified to include either (1) one or two additional J test result; (from actual testing or I
from the literature) at S test temperature of at least T-RTNDT = 150 % or (2) an Appendix G type analysis that demonstrates the adequacy of the maximum experimental K values obtained in this investigation forthematerialasusedikDactual componen*.s at normal full power operating conditions.
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