NRC-88-0084, Deletes Commitment Made in to Change Actuator on RCIC Valve F012,in Response to IE Bulletin 85-003.Design Change to RCIC Sys Will Be Implemented During Local Leak Rate Test Outage to Remove Power to RCIC Valve F012

Deletes Commitment Made in to Change Actuator on RCIC Valve F012,in Response to IE Bulletin 85-003.Design Change to RCIC Sys Will Be Implemented During Local Leak Rate Test Outage to Remove Power to RCIC Valve F012

ML20151C629
Person / Time
Site:	Fermi
Issue date:	04/08/1988
From:	Sylvia B DETROIT EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CON-NRC-88-0084 IEB-85-003, NUDOCS 8804130110
Download: ML20151C629 (3)

Text

_ _ _ _ _ _ _ _ _ _ _ _____ - __

e 8. Ralph Sylvl3 e- Group ve Pres dent 6400 North Demi Edison ~mnarraeRQh*ay - - ' "

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April 8,1988 NRC-88-0084 L

t U. S. Nuclear Regulatory Commission i Attn Document Control Desk Washington. D. C. 20555

References:

1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43 ,

2) IE Bulletin 85-03, November 15, 1985, MOV Common Mode Failures During Plant Transient Due to Improper Switch Settings.  !

3) Detroit Edison Letter to NRC. NRC-87-0095, November 17, 1987, Response to IE Bulletin 85-03.

Subject:

IE Bulletin 85-03 Updated Response RCIC Valve F012 The purpose of this letter is to delete the commitment made in Reference 3 to change the actuator on the Reactor Core Isolation

. Cooling (RCIC) Valve F012. Detroit Edison is implementing a decign change to the RCIC system during the LLRT outage to administrative 1y remove power to the motor-operated RCIC valve F012 (E51-F012). The  !

valve will normally be maintained in the open position. This design change does not alter RCIC system performance and precludes the need  ;

to provide a higher capacity actuator for the RCIC F012 valve as  !

described in Item b of Reference 3. Pertinent information associated  !

with this design change is discussed below.

t As stated in Reference 3, the RCIC F012 valve does not fall within the f scope of IE Bulletin 85-03. We included RCIC F012 within our response l to the Bulletin because the entire RCIC system was evaluated in response to the Bulletin. Reference 3 evaluated the RCIC F012 valve to be acceptable as-is, but long-term considerations warranted l replacing the original actuator with one of higher thrust rating.

The RCIC design change is being implemented for two reasons. First, the replacement actuator could not be obtained in time for installation during the LLRT outage (Outage 88-01) . Second, it has  !

recently been determined (February 1988) that the RCIC F012 actuator l is sized for a valve differential pressure drop which is lower than i the design value stated in UFSAR Section 5.5.6.2.2. The actuator on j l

'8804130110 880408 '

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USNRC 8 April 8, 1988 NRC-88-0084 Fage 2 RCIC F012 was sized for a pressure drop of 1000 psid whereas the UFSAR design _value is 1280 psid. The design change being implemented will provide for maintaining control room valve position indication while removing power from the valve.

The attached simplified flow diagram is provided as a reference to identify valve E51-F012 and its function in the RCIC system.

The RCIC F012 valve is listed in Technical Specification Tables 3.4.3.2-1 and 3.4.3.2-2 as a pressure isolation valve. These tables are referenced by Section 3.4.3.2. The valve can perform the isolation function within four hours, as required, by either of two possibilities manual operation of the E51-F012 handwheel at the valves or temporarily re-energizing the motor operator.

Valve E51-F012 will continue to be periodically stroke tested and leak tested in accordance with Technical Specifications 4.0.5 and 4.4.3.2.2, respectively.

If you have any questions, please contact Ms. Lynne S. Goodman at (313) 586-4211.

Sincerely, Y

Enclosure cc: Mr. A. B. Davis Mr. R. C. Knop Mr. T. R. Quay Mr. W. G. Rogers l

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