ML20087F369

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Interim Deficiency Rept,Item 114 Re Possible Overpressurization of North RHR HX (Pis E11-01-B001A). Initially Reported on 840124.Leakage Observed Coming Through Insulation in HX Shell Flange.No Piping Damage Found
ML20087F369
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 03/07/1984
From: Wells D
DETROIT EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
114, QA-84-0087, NUDOCS 8403190079
Download: ML20087F369 (2)


Text

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c . f Donald A. Wells varawr Owy Aswrance on) '237 %57

= 2000 Second Avenue f Detroit. Michigan 48226 1 m 3) 237-eor;o March 7, 1984 QA-84-0087 Mr. James G. Keppler, Regional Administrator {

Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Subject:

Report of 10CFR50.55(e) Item on Possible Overpressurization of North RHR Heat Exchanger PIS #E11-01-B001A (#114)

Dear Mr. Keppler:

On January 24, 1984, Detroit Edison's Mr. W. R. Wingfield, Quality Engineer - Construction Quality Assurance telephoned Mr. M. Jordon of NRC Region III to report on the possible overpressure of the shell side of the north RHR heat exchanger, PIS #E11-01-B001 A, at the Fermi 2 site.

i Overpressure of the heat exchanger may have occurred during high l pressure hydrostatic testing of attached piping. The high pressure hydro of the attached piping required a test pressure of 1870 + 99 psig. However, the maximum pressure obtained during the test was approximately 1300 psig. The pressure was then reduced to 800 psig (approx.) and the piping under test was inspected for possible leakage. Leakage was observed coming through the insulation in the area of the shell flange of the heat exchanger.

The heat exchanger was outside the boundary of the high pressure test, but had been included in a successful low pressure test (625 psig) performed earlier in the day as part of the same test, package. It appears that a valve used to isolate the heat exchanger from the piping under test may have allowed water to leak through and pressurize the heat exchanger.

Detroit Edison is evaluating the possible overpressure of the north RHR heat exchanger. We have determined that none of the attached piping or valves have been damaged. Engineering is awaiting an evaluation from the vendor to determine if the possible overpressure could have caused damage. Testing procedures have been revised to assure that on future hydro testing, systems outside the test boundary cannot be subjected to accidental pressurization.

il 8403190079 840307 PDR ADOCK 05000341 i 0

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4 James G. Keppler, Regional Administrator

! March 7, 1984

! QA-84-0087 Page 2 r

Another report on this item, either interim or final, will be sent when further information is available. If you have questions

., concerning this matter, please contact Mr. G. M. Trahey, Assistant j Director - Project Quality Assurance.

very truly yours, ,

M i

D. s. w .

cc: Mr. Richard DeYoung, Director Office of Inspection and Enforcement 3'

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i

l' Mr. Paul Byron, Senior Resident Inspector U. S.~ Nuclear Regulatory Commission 6450 North'. Dixie Highway Newport, Michigan 48166 i

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