ML20033B491
| ML20033B491 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/13/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| REF-PT21-81 10CFR-050.55E, 10CFR-50.55E, PLA-960, NUDOCS 8112010464 | |
| Download: ML20033B491 (3) | |
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@ Pennsylvania Power & Light Company Two North Ninth Street
- Allentown, PA 18101 + 2151770-5151 Norman W. Curtis Vice President-Engineering & Construction-Nuclear 215 / 770-5381 November 13, 1981 Mr. R. C. Haynes sD N
f Director, Region I g
/fD U. S. Nuclear Regulatory Commission fI p# /
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631 Park Avenue Dy d
King of Prussia, Pennsylvania 19406
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NOV3 01993, U.E NUctgag ILGULATott SUSQUEHANNA STEAM ELECTRIC STATION
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INTERIM REPORT ON INADEQUATE THICKNESS OF MAIN STEAM b
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RELIEF VALVE DISCHARGE LINE FLANGES yf g([
b ER 100450 FILES 821-10/900-10
'- ! e PLA-960
Dear Mr. Haynes:
This letter serves to provide the Commission with an interim repcrt of a deficiency relating to the inadequate thickness of main steam relief valve discharge line flanges. The deficiency was originally reported under the provisions of 10 CFR 50.55(e) in a telephone call between R. Schwan (PP&L) and J. Wiggins (NRC, Region I) on October 9, 1981. The information contained in this report is submitted pursuant to the provisions of 10 CFR 50.55(e).
The attachment to this letter contains a description of the problem, its cause, safety implications and the corrective action taken to prelcude recurrence.
Since the details of this report provide information relevant to the reporting requirements of 10 CFR 21, this correspondence is considered to also discharge any formal responsibility PP&L may have for reporting in compliance thereto.
We trust the Commission will find the information forwarded by this letter to be satisfactory. We expect to furnish a final report on the deficiency in January, 1982.
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V,ery truly yours,
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N. W. Curtis Vice President-Engineering & Construction-Nuclear BMS:sab
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1 Attachment 8112010464 011113 I[
PDR ADOCK 05000387 i
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Mr. R. C. Haynes November 13, 1981 cc:
Mr. Victor Stello (25)
Director-Office of Inspection & Enforcement U.
S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. G. Mcdonald, Director (1)
Office of Management Information & Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Gary Rhoads U. S. Nuclear Regulatory Commission P.O. Box 52 Shickshinny, PA 18655
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ATTACHMENT TO PLA-960 SUBJECT Inadequate thickness of SSES Unit I Main Steam Relief Valve (MSRV) discharge line flanges.
DESCRIPTION OF DEFICIENCY Bechtel NCR's 8177 and 8204 identified ten of sixteen MSRV discharge line flanges with thicknesses below minimum allowable by the design code. The flanges are 10" x 12", 300 # ANSI rating, expander type manufactured by Taylor Forge and Supplied by ITT Grinnell. The flanges are welded onto the discharge pipe and bolted to the MSRVs.
CAUSE OF DEFICIENCY The specific cause of the deficiency is currently being investigated and will be documented in the final report as required under 10 CFR 50.55(e).
ANALYSIS OF SAFETY IMPLICATION The MSRVs are required to discharge steam into the suppression pool during primary system overpressurization. The undersize flange thickness could cause one or more flanges to fail during an overpressurization incident resulting in a drywell pressurization adverse to plant safety. Thus, this nonconformance appears to be a breakdown in the quality assurance, program and is significant and reportable under 10 CFR 50.55(e).
~~
CORRECTIVE ACTION The ten deficient flanges will be replaced by flanges of proper thickness.
Inspection will be made for other similar flanges to determine the extent of the problem.
FINAL REPORT A final report will be issued when the specific cause of the deficiency and scope of corrective action are clearly determined. It is anticipated that the final report will be released in January, 1982.
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