ML20204G291

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Final Significant Const Deficiency 64 Re Low Safety Injection Tanks,Discharge Flow Rates During Preoperational testing.C-E Analysis Performed Per Nonconformance Rept W3-4636.Flow Rates Acceptable
ML20204G291
Person / Time
Site: Waterford 
Issue date: 04/25/1983
From: Maurin L
LOUISIANA POWER & LIGHT CO.
To: Jay Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, W3I83-0130, W3I83-130, NUDOCS 8305020411
Download: ML20204G291 (3)


Text

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LOUISIANA / 142 DELARONDE STREET P OW E R & L1G HT/ P O BOX 6008

  • NEW ORLEANS. louts!ANA 70174 * (504) 366-2345

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(S April 25, 1983 L v MAURIN Voce Pressdent Nuclear Operations W3I83-0130 Q-3-A35.07.64 g ] ]/h}

Mr. John T. Collins, Regional Administrator, Region IV U. S. Nuclear Regulatory Commission g

I 611 Ryan Plaza Drive, Suite 1000

-II APR 2 81983 Arlington, Texas 76012 h

SUBJECT:

Waterford SES Unit No. 3 Docket No. 50-382

_l Significant Construction Deficiency No. 64

" Safety Injection Tanks, Discharge Flow Rates" Final Report

REFERENCE:

LP&L letter W3I83-0:03 from L. V. Maurin to John T. Collins dated March 28, 1983

Dear Mr. Collins:

In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Final Report of Significant Construction Deficiency No. 64, " Safety Injection Tanks, Discharge Flow Rates".

If you have any questions, please advise.

Very truly yours,

-7 E -2 7 L. V. Maurin l

LVM/ MAL:keh Attachment cc:

1) Director 3)

Mr. E. L. Blake Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555

2) Director 4)

Mr. W. M.

Stevenson Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.

20555 8305020411 830425 PDR ADOCK 05000382 S

PDR

s FINAL REPORT SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 64 SAFETY INJECTION TANKS, DISCHARGE FLOW RATES INTRODUCTION This report is submitted pursuant to 10CFR50.55(e). It describes a condition relative to the rate of blowdown for Safety Injection tanks 1A,1B and 2B encountered during preoperational testing. The blowdown rates fell below the minimum predicted rate established by Combustion Engineering. This problem is considered reportable under the requirements of 10CFR50.55(e). To the best of our knowledge, this problem has not been identified to the Nuclear Regulatory Commission pursuant to 10CFR21.

DESCRIPTION During preoperational testing the duration of blowdown for Safety Injection tanks 1A, 1B and 2B was approximately l'37 seconds for each tank. The maximum predicted duration of blowdown was approximately 101 seconds. Safety Injection Tank 2A performed within the acceptable range of blowdown. This deviation is attributed to the installation of spring loaded check valves installed in the vertical portion of the discharge piping on all three (3) tanks. The high flow resistance.of these valves resulted in the extended duration of blowdown. The fourth tank did not require a spriag loaded check valve since the check valve was installed in a horizontal pipe run, and thus a conventional swing check valve with a lower flow resistance was installed.

SAFETY IMPLICATIONS The ECCS performance was re-evaluated for the limiting break (0.8xDER/PD) using the actual flow resistance K-factors for the Safety Injection lines and demonstrated that the plant meets the 10CFR50.46 acceptance criteria at a peak linear heat generation rate of 13.4KW/ft. This has been documented in the FSAR and included in the proposed Plant Technical Specification.

CORRECTIVE ACTION TAKEN Nonconformance Report W3-4636 was issued on September 29, 1982 to monitor and track this Significant Construction Deficiency.

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Per the recommended disposition of this NCR, Combustion Engineering performed the S.I.T. discharge rate reanalysis and concluded the present installation and the present flow rates are acceptable.

SAR updates were submitted to the USNRC March 25,1983 (Amendment 31).

Nonconformance Report W3-4636 was reviewed, accepted and closed as of March 25, 1983.

This report is submitted as the final status report.

i ys, FINAL REPORT SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 64 SAFETY INJECTION TANKS, DISCHARGE FLOW RATES INTRODUCTION This report is submitted pursuant to 10CFR50.55(e). It describes a condition relative to the rate of blowdown for Safety Injection tanks IA,1B and 2B encountered during preoperational testing. The blowdown rates fell below the minimum predicted rate established by Combustion Engineering. This problem is considered reportable under the requirements of 10CFR50.55(e). To the best of our knowledge, this problem has not been identified to the Nuclear Regulatory Commission pursuant to 10CFR21.

DESCRIPTION During preoperational testing the duration of blowdown for Safety Injection tanks IA, 1B and 2B was approximately l'37 seconds for each tank. The maximum predicted duration of blowdown was approximately 101 seconds. Safety Injection Tank 2A performed within the acceptable range of blowdown. This deviation is attributed to the installation of spring loaded check valves installed in the

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vertical portion of the discharge piping on all three'(3) tanks. The high flow resistance of these valves resulted in the extended duration of blowdown. The fourth tank did not require a spring loaded check valve since the check valve was installed in a horizontal pipe run, and thus a conventional swing check valve with a lower flow resistance was installed.

a SAFETY IMPLICATIONS The ECCS performance was re-evaluated for the limiting break (0.8xDER/PD) using the actual flow resistance K-factors for the Safety Injection lines and demonstrated that the plant meets the 10CFR50.46 acceptance criteria at a peak

' linear heat generation rate of 13.4KW/ft. This has been documented in the FSAR and included in the proposed Plant Technical Specification.

CORRECTIVE ACTION TAKEN Noncenformance Report W3-4636 was issued on September 29, 1982 to monitor and track this Significant Construction Deficiency.

Per the recommended disposition of this NCR, Combustion Engineering performed the S.I.T. discharge rate reanalysis and concluded the present installation and the present flow rates are acceptable.

SAR updates were submitted to the USNRC March 25, 1983 (Amendment 31).

Nonconformance Report W3-4636 was reviewed, accepted and closed as of

-March 25, 1983.

This report is submitted as the final status report.

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