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GULF STATES | GULF STATES UTILITIES COMPANY S E A U M o N r. T E X A S 7 7 7 0 4 P O S T O F F a c t B o x 2 9 51 AREA CODE 713 838 3843 May 7, 1981 RBG - 10,269 File Nos. G9.5 G9.25.1.1 | ||
+ | |||
s Mr. Karl V. Seyfrit, Director F g[ | |||
U.S. Nuclear Regulatory Co= mission Region IV, Office of Inspection & Enforcement Q | |||
.I/Ay y 2 IS8T h-3 C | |||
Arlington, Texas 76011 | 611 Ryan Plaza Drive, Suite 1000 8 | ||
Arlington, Texas 76011 D | |||
==Dear Mr. Seyfrit:== | ==Dear Mr. Seyfrit:== | ||
h River Bend Station - Units 1 and 2 | |||
River Bend Station - Units 1 and 2 | */p g | ||
* Docket Nos. 50-458, 50-459 Safetv-Relief Valve Load Case - Second Pop Phenomenon | * Docket Nos. 50-458, 50-459 Safetv-Relief Valve Load Case - Second Pop Phenomenon In October,1979, Gulf States Utilities (GSU) at the request of the NRC iientified a 10CFR50.55(e) reportable deficiency concerning the safety - relief valve (SRV) second pop phenomenon. Following this identincation, GSU submitted a 30 day iterim report to you in a {{letter dated|date=November 4, 1977|text=letter dated November 4, 1977}}. Since that time GSU has been tracking the General Electric (GE) Company's generic ef forts in resolving the second pop phenomenon and has also been reviewing the applicability of the GE resolution to the River Bend-Station (RBS) design. | ||
In October,1979, Gulf States Utilities (GSU) at the request of the NRC iientified a 10CFR50.55(e) reportable deficiency concerning the safety - relief valve (SRV) second pop phenomenon. Following this identincation, GSU submitted a 30 day iterim report to you in a letter dated November 4, 1977. Since that time GSU has been tracking the General Electric (GE) Company's generic ef forts in resolving the second pop phenomenon and has also been reviewing the applicability of the GE resolution to the River Bend-Station (RBS) design. GSU | GSU has endorsed the GE generic resolution for the RBS design which will incorporate a modification to the SRV control system logic. Details concerning the low-low set relief logic have been provided in the RBS FSAR which van submitted to the NRC on April 24, 1981. This com-pletes our response concerning the 10CFR50.55(e) reportable deficiency. | ||
Sincerely, W | Sincerely, W | ||
E.L. Draper, Jr. V Vice President | E.L. Draper, Jr. V Q | ||
Nuclear Technology ELD /WJR/cb cc: Director of Inspection & Enforcement U.S. Nuclear Regulatory Commission | Vice President Nuclear Technology ELD /WJR/cb cc: Director of Inspection & Enforcement U.S. Nuclear Regulatory Commission g | ||
8105120 W9 | Washington, D.C. | ||
20535 | |||
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8105120 W9 5/# | |||
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Latest revision as of 02:16, 23 December 2024
| ML20008F996 | |
| Person / Time | |
|---|---|
| Site: | River Bend |
| Issue date: | 05/07/1981 |
| From: | Draper E GULF STATES UTILITIES CO. |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8105120489 | |
| Download: ML20008F996 (1) | |
Text
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GULF STATES UTILITIES COMPANY S E A U M o N r. T E X A S 7 7 7 0 4 P O S T O F F a c t B o x 2 9 51 AREA CODE 713 838 3843 May 7, 1981 RBG - 10,269 File Nos. G9.5 G9.25.1.1
+
s Mr. Karl V. Seyfrit, Director F g[
U.S. Nuclear Regulatory Co= mission Region IV, Office of Inspection & Enforcement Q
.I/Ay y 2 IS8T h-3 C
611 Ryan Plaza Drive, Suite 1000 8
Arlington, Texas 76011 D
Dear Mr. Seyfrit:
h River Bend Station - Units 1 and 2
- /p g
- Docket Nos. 50-458, 50-459 Safetv-Relief Valve Load Case - Second Pop Phenomenon In October,1979, Gulf States Utilities (GSU) at the request of the NRC iientified a 10CFR50.55(e) reportable deficiency concerning the safety - relief valve (SRV) second pop phenomenon. Following this identincation, GSU submitted a 30 day iterim report to you in a letter dated November 4, 1977. Since that time GSU has been tracking the General Electric (GE) Company's generic ef forts in resolving the second pop phenomenon and has also been reviewing the applicability of the GE resolution to the River Bend-Station (RBS) design.
GSU has endorsed the GE generic resolution for the RBS design which will incorporate a modification to the SRV control system logic. Details concerning the low-low set relief logic have been provided in the RBS FSAR which van submitted to the NRC on April 24, 1981. This com-pletes our response concerning the 10CFR50.55(e) reportable deficiency.
Sincerely, W
E.L. Draper, Jr. V Q
Vice President Nuclear Technology ELD /WJR/cb cc: Director of Inspection & Enforcement U.S. Nuclear Regulatory Commission g
Washington, D.C.
20535
(
8105120 W9 5/#
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