ML20011A240

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Final Deficiency Rept Re Failure of Two Rigid Sway Strut Paddles to Meet Required Proof Load Testing,Initially Reported on 810528.Affected Sway Strut Paddles in SC-1 Areas Will Be Repaired or Replaced
ML20011A240
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 09/28/1981
From: Matlock R
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, GO2-81-0316, GO2-81-316, NUDOCS 8110080359
Download: ML20011A240 (1)


Text

50.55(e) Report Docket No. 50-397

J Washington Public Power Supply System P.O. Box 968 3000 GeorgeWashingtonWay Richland, Washington 99352 (509)372-5000 September 28, 1981 G02-81-0316 Docket No. 50-397 Mr. R. H. Engelken U. S. Nuclear Regulatory Commission Region'V Suite 202,- Walnut Creek Plaza 1990 North California Boulevard Walnut Creek,_ California 94596

Dear Mr. Engelken:

Subject:

SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 POTENTIALLY REPORTABLE DEFICIENCY -

10CFR50.55(e) #156 RIGID SWAY STRUT PADDLES Your office was informed by phone on May 28, 1981, of a potentially reportable deficiency, regarding the failure in testing below the required proof load of the rigid sway strut paddles.

We forwarded an interim report on this matter on June 29, 1981.

Our' evaluation of this condition has determined that the condition is. not reportable under 10CFR50.55(e). However, a code violation does exist which must be rectified. -The situation is that o' 'ee (3) paddler tested, two (2) failed at less than the required proof load of thirty seven (37) kips. The design load for these paddles is six (6) kips and we feel that with the remaining safety margin this is not a condition "which were it to have remained uncorrected, could have adversely affected the safety of the operations of the nuclear plant."

The approach to resolution of the code violations has been to first identify all the affected sway strut paddles in SC-I areas. Secondly, actual loads are being researched to determine whether or not the design load (six (6) kips) can be derated. This should resolve the concern. The sway strut paddles above derated allowable load will be either repaired or replaced, depending on the number in question. This effort is ongoing and will be completed in the near future.

7 This is our final report on this condition. T 5 f Very truly yours,

/2/gi;&At ll0 R./G. Matlock RGM/SLN/kh Program Director, WNP-2 cc: ' ' M Wi?.~U WS Chin BPA TA Mangelsdorf Bechtel V Stello NRC A Forrest HAPO J Plunkett NRC AD Toth NRC Rg'sidgnt Inspector WNP-2 ND Lewis NRC RE Snaith B&R NY WNP-2 Files V 3 /W 0E d;s gg Dut,

~8110080359 810928 5

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