ML20012A169

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Forwards EAS-03-0190, Core Spray Line Crack Growth Analysis Update for Brunswick Steam Electric Plant Unit 2. Util Believes That Plant Can Continue to Operate Safely W/Crack During Next Fuel Cycle & No Restrictions Required
ML20012A169
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 02/23/1990
From: Loflin L
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20012A170 List:
References
IEB-80-13, NLS-90-048, NLS-90-48, NUDOCS 9003080435
Download: ML20012A169 (2)


Text

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Carolina Power & Light Company SERIAL:' NLS-90-048 FEB 2 31090 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington,'DC' 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NO. DPR-62 RESPONSE TO IE BULLETIN 80-13 EXAMINATION OF CORE SPRAY SYSTEM SPARGERS Gentlemen:

'in accordance with IE Bulletin 80-13, a visual inspection (Periodic Test 90.1)'

of the core spray spargers and in-vessel core spray piping of the Brunswick

' Steam Electric Plant Unit 2=(BSEP-2) was performed during Reload 8.

The crack 11ndication previously identified on the north core spray.line has indicated 4

. growth.

. An evaluation of, the. safety significance of the crack has been performed.

.This. evaluation is provided in Attachment 1.

The' technical basis to support

the continued structural integrity of the core spray line for all normal and injection conditions is provided.

A' discussion of the-possible consequences of potential loose pieces from a cracked pipe and the consequences of a postuinted loss of coolant accident (LOCA) with a crack in the' core spray-piping are discussed.

The structural analysis concludes that the integrity of the core spray piping will be_ maintained for all conditions of. operation during the next operating

' cycle.

The loose piece analysis shows that the probability of unacceptable control rod interference due to loose parts has not changed from the previous

' evaluation.

z Based on the updated analysis, CP&L believes that BSEP-2 can continue to

' safely' operate with this crack during the next fuel cycle and that no operational changes'or restrictions are required.

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9003080435 900223 PDR ADOCK 05000324

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O PNU f

'l 411 Fayetteville Street

  • P. O. Box 1551
  • Raleigh. N C. 27602

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  • Document Control = Desk

-NLS-90-04B / Page 2 Please refer any questions regarding this submittal to Mr. M. R. Oates at (919) 546-6063.

Yours very truly,

/0 L.

flin Man er Nuclear icensing r.

DBB/eco (620ECC)

Enclosure oc:

Mr.'S..D.:Ebneter Mr. W. H. Ruland Mr. E. G.'Tourigny

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