ML20207S434

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Informs of Inaccuracy in Technical Evaluation Rept Submitted W/Ra Clark Forwarding Safety Evaluation of Util Response to IE Bulletin 80-04.Clarification to Technical Evaluation Rept Does Not Affect Conclusion Reached by Rept
ML20207S434
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 03/12/1987
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To: Lear G
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-87-024, CON-NRC-87-24 IEB-80-04, IEB-80-4, TAC-46851, TAC-46852, VPNPD-87-097, VPNPD-87-97, NUDOCS 8703190444
Download: ML20207S434 (2)


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lHsconsin Electnc rom coww 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE.WI 53201 (414) 221-2345 VPNPD-87-097 NRC-87-024 March 12, 1987 U. S. NUCLEAR REGULATORY COMMISSION Document Control Desk Washington, D.

C.

20555 Attention:

Mr. George Lear, Director PWR Project Directorate 1 Gentlemen:

DOCKETS 50-266 AND 50-301 AUXILIARY FEEDWATER PUMP RUN-OUT PROTECTION POINT BEACH NUCLEAR PLANT While conducting an operating experience review of an NRC system safety assessment report on the auxiliary feedwater system at another operating plant, we noted an inaccuracy in the Technical Evaluation Report (TER) for Point Beach, which was transmitted as an attachment to Robert A. Clark's letter dated October 8, 1982.

This letter included the NRC's safety evaluation of our response to IE Bulletin 80-04, " Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition."

At Page 13, the TER states, "Each of the AFW pumps supplies auxiliary feedwater to the steam generators through a motor-operated valve which is normally throttled open.

These valves limit the flow to about 400 gpm and prevent the pumps from experiencing run-out flow conditions."

While this statement is correct for the steam-driven AFW pumps, it is not accurate for the motor-driven AFW pumps.

Auxiliary feedwater flow from each of the motor-driven pumps is limited by air-operated valves in the pump discharge line.

These air-operated valves are normally throttled automatically to maintain pump discharge pressure at 1200 psig.

This provides approximately 200 gpm to the steam generators at saturation pressure for no-load T average and, thus, protects these pumps from run-out conditions.

In the case of having both motor-operated AFW pumps lined up to one unit, the total auxiliary feedwater flow from the electrically driven pumps would be nominally 400 gpm (200 gpm per steam generator).

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NRC Document Control Desk March 12, 1987 Page 2

.We believe this clarification to the statements made in the TER does not affect the conclusion reached by that report.

The AFW pumps are still protected from the effects of run-out flow conditions and can be expected to perform their intended function during a main steam line break event.

Very truly yours,

( V

,/

C. w. ra Vice President Nuclear Power copios to NRC Resident Inspector Region III NRC Regional Administratot i

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