ML20082Q724
| ML20082Q724 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 12/01/1983 |
| From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, 10CR-50.55E, 259, GO2-83-1105, NUDOCS 8312120316 | |
| Download: ML20082Q724 (2) | |
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Washington Public Power Supply System P.O. Box 968 3000 GeorgeWashingtonWay Richland, Washington 99352 (509)372-5000 December 1, 1983 G02-83-1105
' 5; Mr. J. B. Martin E
E 58 Regional Administrator 2
M U.S. Nuclear Regulatory Commission 5
E Region V 1450 Maria Lane, Suite 210 cn Walnut Creek, California 94596 C3
Subject:
NUCLEAR PROJECT N0. 2 10CFR50.55(e) REPORTABLE CONDITION #259 INCOMPLETE ANCHOR BOLT ANALYSIS - RHR HEAT EXCHANGERS
Reference:
Telecon dated November 1, 1983, R.T. Johnson to Bob Dodds In accordance with the provisions of 10CFR50.55(e), your office was informed, by the reference, of the above subject condition. The attach-ment provides the Project's interim response on Condition #259. A final response, including the analysis results,will be transmitted December 6, 1983.
If there are any questions concerning this matter, please contact Roger Johnson, WNP-2 Project QA Manager, (509) 377-2501, extension 2712.
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G. C. Sorensen Manager, Regulatory Programs RTJ/kd
Attachment:
As stated cc:
W.S. Chin, BPA N.D. Lewis, EFSEC A. Toth, NRC Resident Inspector Document Control Desk, NRC f
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8312120316 031201 PDR ADOCK 05000397 hl S
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llASHINGTON PUBLIC P011ER SUPPLY SYSTEi-1 NUCLEAR PROJECT NO. 2 DOCKET NO. 50-397 LICENSE NO. CPPR-93 10CFR50.55(e) REPORTABLE CONDITION #259 INCOMPLETE ANCHOR BOLT ANALYSIS - RHR HEAT EXCHANGERS INTERIM REPORT Description of the Deficiency The-design reverification review identified the lack of calculations for the RHR heat exchanger lower anchor bolt washer plate. Burns and Roe, as part of the corrective action to denonstrate no tension loads existed on the anchor bolts, requested General Electric's confiruation on the design loads. General Electric has indicated that as a result of nozzle loading on the vessel, the original 10,000 pound tension or uplift load on the heat exchanger may be signif-icantly larger.
Safety Significance The structural members supporting the heat exchanger may be inadequate to meet certain loading conditions imposed on the vessel. An extensive evaluation is required to deternine if the existing design is adequate, therefore, the condi-tion is considered potentially reportable.
Cause for the Deficiency The bounding conditions for the structural design may have been inadequate, due to the problen of establishing and quantifing the condition, which would produce the worse case interface condition between the vessel and the structure.
Action to Prevent Recurrence The design reverification process was to assure that the aethods utilized by the designers were idequate. IJhere deficiencies have been identified, they have hen cycluated for their generi: igli:aticr.s and, as requirF. n'ditionel reviews have been conducted to ensure the condition does not affect design else-where. No further corrective action is considered necessary at this tiae.
-Corrective Action General Electric is performing a coupled analysis utilizing the "At-Built" condi-tions of the RHR heat exchanger to establish the worse case loading condition on the heat exchanger anchor bolts and the structure.
The evaluation and any corrective action will be complete prior to fuel load.