ML20083F361
| ML20083F361 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 12/14/1983 |
| From: | Sorensen G, Sorensen G, Sorenson G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, 259, GO2-83-1161, NUDOCS 8312300274 | |
| Download: ML20083F361 (2) | |
Text
,
~
t-RECOVED Washington Public Power Supiply System P.O. Box 968 3000 GeorgeWashingtonWay Richland, Washington 99352 (509)372-5000 IW DEC 19 PM I? 53 December 14, 1983 G02-83-1161 RESIGU'W s
~
Mr. J. B. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596
Subject:
NUCLEAR PROJECT N0. 2 10CFR50.55(e) NON-REPORTABLE CONDITION #259 INCOMPLETE ANCHOR BOLT ANALYSIS - RHR HEAT EXCHANGERS
Reference:
1.
Telecon dated November 1, 1983, R.T. Johnson to Bob Dodds.
2.
Letter G02-83-1105, dated 12/1/83, G.C. Sorensen to y-J.B. Martin.
3 In accordance with the provisions of 10CFR50.55(e), your office was informed by the references of the above subject condition. The attachment provides the Project's final response on Condition #259.
If there are any questions concerning this matter, please contact Roger Johnson, WNP-2 Project QA Manager, (509) 377-2501, extension 2712.
s
] g G. C. So ensen Manager, Regulatory Programs JGT/kd
Attachment:
As stated cc:
W.S. Chin, BPA N.D. Lewis, EFSEC A. Toth, NRC Resident Inspector Document Control Desk, NRC 8312300274 831214 gDRADOCK05000 hL '2f
\\\\
.g,
. WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT N0.'2 DOCKET NO. 50-397 i
LICENSE N0. CPPR-93 10CFR50.55(e) CONDITION #259 INCOMPLETE ANCHOR BOLT ANALYSIS - RHR HEAT EXCHANGERS Description of Deficiency Revised loads transmitted by GE for the RHR Heat Exchanger-lower supports were not fully evaluated by Burns and Roo for their effect on the anchor bolts. Specifically, the anchor bolt design load in the vertical up direc-tion was 10 kip / bolt whereas the revised load provided by GEBR-2-81-189 was 76.22' kip / bolt.
Date and Method of Ciscovery This condition was first identified by the Supply System during " Design Reverification" activities and wa:: documented as Potential Findings Report (PFR) RHR-25 dated April 5, 1983.
Safety Implication Overloading of the anchor bolts could result in failure of the RHR heat exch' angers during post accident conditions. Should both heat exchangers sustain significant damage reactor cooldown would require the use of non-safety related systems.
Cause of Deficiency This is considered to be an oversight with no generic implications.
Action to Prevent Recurrence None required.
Corrective Action Since.the loads that the heat exchanger impart to the building structure are dependent on loads input to the heat exchanger from attached piping, a coupled analysis was performed by GE to determine actual loads to the anchor bolts. Since the coupled analysis was a time comsuming task, contin-gency action was taken to modify the anchor bolts and washer plate assembly to be able to transmit the maximum loads (48 kip / bolt) equivalent to the capacity of the structural beams to which they attach (PED-215-CS-6492).
. The results of.the coupled analysis determined the maximum vertical up load
, to'be 35 kip / bolt which is considerably larger than the 10 kip / bolt original design load. However, Burns and Roe recalculated and determined the original
- anchor bolt design to actually be capable of witiistanding 38 kip / bolt wnich is greater than the coupled analysis load of 35 kips / bolt. Therefore, the original design is adequate and this condition is considered to be not report-able under 10CFR21.
~
. -.