ML20211A870
| ML20211A870 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/06/1986 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| GN-1003, GN-1103, IEB-79-21, NUDOCS 8610170050 | |
| Download: ML20211A870 (2) | |
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Geortpa Power Company Post Offec3 Bon 282 7.t,.
-A Georg3 30830 Telephone 404 554 9961 404 724 8114 Southern Company Services,Inc.
Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 8704011 Vogtle Project October 6, 1986 Director of Nuclear Reactor Regulation File: X7BC35 Attention: Mr. B. J. Youngblood Log:
GN-1103 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission
. Washington, D.C.
20555 REF: BAILEY TO DENTON, GN-1088, 9/26/86 l
NRC DOCKET NUMBERS 50-424 AND 50-425 l
l CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANI - UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION:
IE BULLETIN 79-21
Dear Mr. Denton:
The following is an expansion of the referenced letter as requested by your staff in a telecon on October 1,1986.
The maximum distance from the condensate pot centerline to the first anchor point of the flexible hoses (for narrow range water level measurement systems only) is 32 inches (LT-549). Measurement accuracy is approximately 1 inch.
Further, the thermal growth of the steam generators is approximately 2 inches.
The narrow range reference leg heatup tables that were generated for incorporation into the Vogtle Emergency Operating Procedures (EOP) were used for calculation of the potential errors.
Assume a cold leg reference leg length of 128 inches (130 inch hot). As stated above, the longest vertical rise (cold) from the centerline of the
~
condensate pot to the first anchor point of the flexible hose for a narrow range channel is 32 inches cold (34 inches hot) plus 1 inch measurement uncertainty.
Per Figure 6.2.1-33 of Chapter 6 of the Plant Vogtle FSAR, the peak containment temperature following a secondary high energy line rupture is 352*F. Assuming no insulation, the maximum reference leg heatup at 352*F at an assumed narrow range level of 25% of span (assuming a conservative 600 psig secondary pressure) is 15% of span.
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p
. 's Director of Nuclear Reactor Regulation File: X7BC35 October 6,1986 Log:
GN-1103 Page 2 The fracture of the reference leg that is uninsulated is 0.269.
Hence, the reference leg induced error to the uninsulated portion is approximately 4% of span.
Furthe rmore, it was conservatively assumed that the water in that portion of reference leg with insulation heats up a maximum of 20*F within 5 minutes following the secondary high energy line rupture. Again based upon the E0P reference leg heatup error tables, the maximum reference leg heatup at 130*F at an assumed narrow range level of 25% of span (assuming a conservative 600 psig secondary pressure) is 1.3% of span.
The fraction of the reference leg that is insulated is 0.731.
Hence, the reference leg induced error due to the insulated portion is approximately 1%
.of span.
Thus, the total error due to reference leg heatup is 5% of span.
If your staff requires any additional information, please do not hesitate to contact me.
S
- erely,
. it.
J. A. Bailey Project Licensing Manager JAB /sm xc:
R. E. Conway NRC Regional Administrator R. A. Thomas NRC Resident Inspector J. E. Joiner, Esquire D. Feig B. W. Churchill, Esquire R. A. McManus M. A. Miller (2)
L. T. Gucwa B. Jones, Esquire Vogtle Project File G. Bockhold, Jr.
0767V
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