TXX-6887, Final Deficiency Rept CP-87-107 Re Auxiliary Feedwater Design Pressure.Initially Reported on 870924.Engineering Evaluation Performed & Issue Determined Not Reportable Per 10CFR50.55(e)
| ML20236G141 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/27/1987 |
| From: | Counsil W, Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CP-87-107, TXX-6887, NUDOCS 8711020435 | |
| Download: ML20236G141 (2) | |
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- wuayc. counsu October 27, 1987
. lincutive Vkt President
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U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 i
AUXILIARY FEEDWATER DESIGN PRESSURE SDAR:
CP-87-107 (FINAL REPORT)-
Gentlemen:
On September 24, 1987, we verbally notified your Mr. I. Barnes of a deficiency involving the calculated maximum Auxiliary Feedwater (AFW) System pressure which may exceed the design pressure of components within the AFW system. On October 27, 1987, we verbally notified your Mr. H. S. Phillips that our-written report.due to be submitted on October 26, 1987, would not be submitted until October 27, 1987, due to an administrative oversight.
An engineering evaluation has determined that this issue is not reportable under the provisions of 10CFR50.55(e).
The design validation process of the auxiliary feedwater system and calculation.16345-ME(B)-022, Case SPDP #3, revealed that the maximum system pressure for motor driven auxiliary' feedvater pumps CP1-AFAPMD-01 and CP1-AFAPMD-02 and for their bypass breakdown orifices CP1-AFORB0-01 and CP1-AFORB0-02 exceeds the design pressure of these components.
Specifically, the component's design pressure is 1600 psig, while the maximum calculated system pressure, corresponding to the pump shut-off head at maximum water level in the condensate storage tank, amounts to 1613.1 psig.
In case of an accident, when' the motor driven pumps arc required to operate, this could have ieu to overpressurization of the pumps and orifices.
The manufacturer of the subject pumps and orifices, Ingersoll-Rand (I-R), has confirmed that these components can sustain the calculated overpressure
.without damage to the components.
Therefore, were this condition to remain uncorrected, it could not adversely affect the safety of operations of the gj plant and therefore is not reportable under the provisions of 10CFR50.55(e).
(fl jfT B711020435 871027 i
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October 27,;1987
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Page 2 of 2 No rerating1of these components or other corrective action'is required.
'l Records supporting.this conclusion are available.for review by your. inspectors t
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Very truly yours, j
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'W. G. Counsil By:
D. R. Woodlan
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Supervisor, Docket Licensing 1
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'c -'Mr. R..D. Martin,. Region'IV l
' Resident Inspectors, CPSES (3)
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