ML20012B673

Responds to NRC Bulletin 88-011,Action 1.a Re Insp of Surge Line to Determine Discernible Distress or Structural Damage & Advises That Neither Surge Line Nor Affiliated Hardware Suffered Any Discernible Distress or Structural Damage

ML20012B673
Person / Time
Site:	Waterford
Issue date:	03/07/1990
From:	Burski R LOUISIANA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-88-011, IEB-88-11, W3P90-0214, W3P90-214, NUDOCS 9003160093
Download: ML20012B673 (2)

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I . Louisions Power & Light Company.-f 317 Daronne Street .

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. P. O. Box 60340 Now Orleans, LA 70160 0340 ' L!

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g R. F. Burski - - .

Nuclear Safety & Rogulatory Affairs-

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< j March'7, 1990 'l

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. U.S. Nuclear Regulatory Commission

- ATTN: : Document Control Desk '

Washington, D.C. 20555

' Subjects _ Waterford 3 SES_

,l l . Docket No. 50-382 (

4[. License No. NPF-38

~NRC Bulletin 88-11, Action 1.a Results

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9 Gentlemen:

NRC Bulletin 88-11 requires licensees to take actions based-on concerns' over stratified' flow phenomenon in pressurized water reactor plantsn'The. ,[

f concerns center on the " surge line" between one' reactor coolanc loop hot'-

t 1eg and the-pressurizer. LP&L's response to all-requested actions,'

except:one, went to-the NRC on August 28~ _1989 (re W3P89-1533) . : The one remaining.) Action ;1.a of Bulletin 89-11, requires a VT-3 (visual) '

inspection.ofLthe: surge'line to determine whether any discernible distress or structural' damage exists. . Stratified flow has. bent surge _ lines atiother-  :

Lplants.' : The term " surge line",.in_this-letter, covers the pipe;itself, its 1 supports, whip restraints and' anchor bolts.- ,

!The VT-3' surge line inspection occurred during the last.Waterford refueling '

e ' outc3e, specifically_ on October -3 'and ' 4, 1989. : - A Level" Ill'. qualified l

, inspector performed.the VT-3 with the assistance of a Level I inspector. -A ,

= senior' engineer experienced in the issue of thermal stratification-in pressurizer surge: lines supervised the data gathering and reduction.-lThe: ,

samecsenior: engineer was also familiar:with'the Waterford system.- The-

. final inspection .results became available on January .12,1 1990.. .

The inspectors looked for-discernible distress or structural' damage byf gathering 1 data to. compare to 1985 measurements. They took special-care.at-whip. restraint locations where contact with the pipe was possible. They examined. spring hangers for damage and operability and'also recorded their spring settings. _ Gap measurements at the D-ring wall penetration, and the

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large=and small gap whip restraints were made using a metal ruler with 0.016 inch gradations. The inspectors checked the measurements twice l

before recording them. These measurements' resemble those taken in the 1985 baseline.

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W3PPO-0214 NRC Bulletin 88-11, Action 1.a Results

'Page'2 '

. LP&L possesses a comparison bet' ween the 1989 and 1985 measurements. While some of-the-measurements indicate a possible shift in~1ocation,'that shift-

'is well within~that predicted during initial plant startup. Sliding bearings allow the reactor vessel and steam generator to move away from-the construction set location during a heatup and cooldown cycle. Resistance offered by the. sliding bearings accounts for equipment not returning to its original position and'the shifts seen in the 1989 inspection.

' Based on'the inspection data review and evaluation dated January 12, 1990, neither:the Waterford surge line, nor its affiliated hardware suffered any

' discernible distress or structural damage. Therefore, the surge line is in a safe-operating condition.

If there are any questions regarding this information, please contact me or

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Mr. Larry Laughlin at (504) 464-3499._

Very=truly yours,

..(E V RFB/SEF/ssf cci Messrs. R.D. Martin,~NRC Region IV F.J. Hebdon,1NRC-NRR D.L. Wigginton, NRC-NRR E.L. Blake W.M. Stevenson-NRC: Resident Inspectors Office 5

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