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Text
AEC DX BKIOiJ FOR PART 0 DOCKET YA~x" L Tr AQOBARX r ORI>A COAVBROL ZIO; 1810
. TB(M: DAM OF DOC: DATE REC'D LTR Rochester Gas h Electric Corp.
(Rochester.,"-.,N.. Y., 14604 T 3-15-73 3-19-73 TO e ORIG CC E" h7 A.C riJi3 1 Mr. Skovholt 1 signed.
CLASSY U PROP Xi0 Idiocy T HO CXS REC'D DOCiKT iio:
4o 5o-244 DESQRiPiION: EitCLOSURES; I(tr re.our 9-12>>72 ltr, trans the following: REPORT: "RGAE - Ginna Station Crd.t, No. 1 Main Steam Header Dynasdc Load Factor Analysis'3M 3 ~ 15 <<73 e NOTE: DIST PER.S. TEETS
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-'%"age '% cy ROCHESTER GAS AND ELECTRIC CORPORATION D 89 EAST AVENUE, ROCHESTER, N.Y. 14604 GRANGER E. GREE/ TELEPHONE VICE PRESIDENT AREA CODE 7le 546.2700 March 15, 1973 Mr; Donald J.
Director for Operating Reactors Skovholt'ssistant Directorate of Licensing U. S. Atomic Energy Commission l<ashington, D. C. 20545
Subject:
Main Steam Safety Valve Supports R.E. Ginna Nuclear Power Plant Unit No. 1 Docket 50-244
Dear Mr. Skovholt:
In response to your letter of September 12, 1972, requesting additional information on Main Steam Safety Valve Supports, we here-with submit forty (40) copies of a supplementary report: "RG&E-Ginna Station Unit No.' Main Steam Header Dynamic Load Factor Analysis" dated March 15, 1973.
The attached report on the main steam safety valves supplements two previous documents, "Report on the Main Steam Safety Valve" submitted June 5, 1972, and "Addenda to the Gilbert Stress Report" submitted June 19, 1972. Furthermore, a meeting was held in your office on November 27, 1972 to review the additional information requested on the main steam and pressurizer safety valve analysis in your letter of September 12, 1972. At this meeting it was agreed that a dynamic analysis would be performed on the main steam header to determine the dynamic load factors (DLF) occurring at the safety valve-header inter-face. This dynamic analysis would confirm the adequacy of the original structural analysis submitted on June 5, 1972 in which a system with a single degree of freedom and a conservative DLF of 2.0 had been assumed.
This report indicates that for the Ginna Station main steam header the maximum upper bound load factors are 1.16 and 1.50 for a single and multiple valve discharge respectively. In calculating the DLF, this analysis has accounted for the contributions to the piping response given by all the signifi.cant vibrational modes of the structure for a single valve and multiple valve discharge. The report concludes that nocerg
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ROCHESTER GAS AND ELECTRIC P. SHEET NO.
oATE March 15, 1973 To Mr. D. J . Skovholt the existing valve/header design is conservative based on a calculation of the actual dynamic upper bound values of DLF. The effects of multiple safety valve discharges should be considered since the'analysis showed a possible 305 increase in load factor due to actuation of a second valve.
The actual load factor achieved in the system should be significantly lower than the upper bound values predicted since damping will reduce the maximum contribution from each mode and for multiple valve discharge the time between valve discharges must be exactly equal to a period of one of the primary modes for the maximum
'I response to occur.
Ver ruly yours, M anger . r n
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