ML20072C489

Final Significant Const Deficiency Rept 48,R-1 Re Design Application of Break Flanges at Elevated temps.Forty-five Flanges W/Type 316 SS Matl Replaced & Installed Bolts Replaced W/High Strength Bolts for Addl 21 Flanges

ML20072C489
Person / Time
Site:	Waterford
Issue date:	02/28/1983
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, W3I83-0066, W3I83-66, NUDOCS 8303080455
Download: ML20072C489 (3)

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~U February 28, 1983 t. v MAunin Vice President Nuclear Operatsons W3I83-0066 Q-3-A35.07.48 Mr. John T. Collins, Regional Administrator Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012

SUBJECT:

Waterford SES Unit No. 3 Docket No. 50-382 Significant Construction Deficiency No. 48 R-1

" Design Application of Break Flanges at Elevated Temperatures"

REFERENCES:

LP&L letter W3182-0122 dated December 17, 1982, L. V.Maurin to John T. Collins LP&L letter W3I83-0017 dated January 24, 1983, L. V.Maurin to John T. Collins

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. 48 R-1,

" Design Application of Break Flanges at Elevated Temperatures".

If you have any questions, please advise.

Very truly yours,

///4N L. V. Maurin LVM/WAC:keh ec: 1) Director 3) E. L. Blake Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (with I copy of report)

2) Director 4) W. M. Stevenson g Office of Management g Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (/

[h (with 15 copies of report) /

8303080455 830228 PDR ADOCK 05000382 S PDR

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-0 FINAL REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 48 R-1

" DESIGN APPLICATION OF BREAK FLANGES AT ELEVATED TEMPERATURES" ,

INTRODUCTION ~

This report is submitted pursuant to 10CFR50.55(e). It describes a deficiency in the flange material used in the Reactor Coolant, Safety Injection and Chemical and Volume Control Systems. 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 NRC pursuant to 10CFR21.

DESCRIPTION During the installation of break flanges in the field, it was discovered that 4 type 304 stainless steel flanges had been installed in the above mentioned systems, where the maximum operating conditions exceeded the pressure / temperature ratings of the installed flanges. 'These flanges did not meet the ANSI B 16.5 pressure /

temperature ratings as required by the ASME code. Examination of ae station

~ piping specification and the piping line list indicated that the correct flanges were specified in these documents for large bore piping. The error was introduced in the preparation of large bore isometrics by the piping fabricator. For small bore piping, a material conflict was noted between the design drawings and the piping line list. These documents were utilized by the piping fabricator to develop small bore piping isometrics.

i SAFETY IMPLICATIONS t

The subject flanges are located in the Reactor Coolant Safety Injection, and Chemical and Volume Control systems. Failure of these flanges could cause a LOCA, degrade operation, or render a safety system inoperable. Therefore, the deviation could adversely affect the safety of the plant if lef t uncorrected.

CORRECTIVE ACTION The following corrective action was taken to correct this deficiency:

1) Nonconformance Report (NCR-W3-3302 S/1) was issued to identify, disposition, and track all flsnges that were not within allowable design limits.

- 2) The flanges were analyzed by Ebasco's Stress Analysis Group in accordance

with the ASME Section III Code paragraphs NB/NC/ND-3658. These paragraphs give a methodology to evaluate a flanged joint, regardless of whether i it-meets S16.5 rating or not.

I 3) As a result of this analysis, corrective actions were recommended for the flanged joints which did not meet the code requirements. These corrective actions included replacement of 45 flanges with type 316 SS material and replacement of the installed bolts with high strength bolts for an additional 21 flanges.

4) As a result of the flange analysis and the corractive actions taken therein,

all flanges now meet the requirements of the ASME Section III code.

This Report is submitted as the final report.

.- - , - _ _ , . - , _ , _ , , - - . _ . _ . . _ . . , _ . _ . _ , . _ , _ _ _ _ _ , _ _ _ _ _ . _ _ , , _ , , . _ ,,_......-m_. - _ - . . _ . , _ . . _ _ - _ . _ . _ , - _ . , _.. -_,

FINAL REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 48 R-1

" DESIGN APPLICATION OF BREAK FLANGES AT ELEVATED TEMPERATURES" INTRODUCTION This report is submitted pursuant to 10CFR50.55(e). It c'.escribes a deficiency in the flange material used in the Reactor Coolant, Safety Injection and Chemical and Volume Control Systems. 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 NRC pursuant to 10CFR21.

DESCRIPTION During the installation of break flanges in the field, it was discovered that type 304 stainless steel flanges had been installed in the above mentioned systems, where the maximum operating conditions exceeded the pressure / temperature ratings of the installed flanges. These flanges did not meet the ANSI B 16.5 pressure /

temperature ratings as required by the ASME code. Examination of the station piping specification and the piping line list indicated that the correct flanges were specified in these documents for large bore piping. The error was introduced in the preparation of large bore isometrics by the piping fabricator. For small bore piping, a material conflict was noted between the design drawings and the piping line list. These documents were utilized by the piping fabricator to develop small bore piping isometrics.

SAFETY IMPLICATIONS The subject flanges are located in the Reactor Coolant, Safety Injection, and Chemical and Volume Control systems. Failure of these flanges could cause a LOCA, degrade operation, or render a safety system inoperable. Therefore, the deviation could adversely affect the safety of the plant if left uncorrected.

i CORRECTIVE ACTION The'followin2 corrective action was taken to correct this deficiency:

1) Nonconformance Report (NCR-W3-3302 S/1) was issued to identify, disposition, l and track all flanges that were not within allowable design limits.

l l 2) The flanges were analyzed by Ebasco's Stress Analysis Group in accordance

with the ASME Section III Code paragraphs NB/NC/ND-3658. These paragraphs l give a methodology to evaluate a flanged joint, regardless of whether j it meets B16.5 rating or not.

l

3) As a result of this analysis, corrective actions were recommended for the flanged joints which did not meet the code requirements. These corrective _

actionr, included replacement of 45 flanges with type 316 SS material and

replacement of the installed bolts with high strength bolts for an additional l 21 flanges.

4) As a result of the flange analysis and the corrective actions taken therein, all flanges now meet the requirements of the ASME Section III code.

l This Report is submitted as the final report.

l

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