ML20138L788

Forwards SER Re Valve Relief Request VR-45-R1 Where Licensee Proposed to Perform Disassembly & Insp of Associated Check Valves in Lieu of Stroke Testing Required by Code.In Accordance W/Gl 89-04,position 2 Relief Not Required

ML20138L788
Person / Time
Site:	Fermi
Issue date:	02/19/1997
From:	Hannon J NRC (Affiliation Not Assigned)
To:	Gipson D DETROIT EDISON CO.
Shared Package
ML20138L791	List: ML20138L788 ML20138L796
References
GL-89-04, GL-89-4, TAC-M97306, NUDOCS 9702250079
Download: ML20138L788 (3)

Text

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• February 19 1997 Mr. Douglas R. Gipson Senior Vice President Nuclear Generation Detroit Edison Company 6400 North Dixie Highway Newport,-Michigan 48166

SUBJECT:

FERMI 2'- SAFETY EVALUATION OF PORTIONS OF REVISION 3, CHANGE 11 TO 4

THE PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. M97306)

Dear Mr. Gipson:

^

On November 1, 1996, you submitted Revision 3, Change 11 to the Fermi 2 pump i and valve inservice testing program. Some of the changes included in this  ;

document were in response to an NRC staff safety evaluation of pump and valve relief requests dated May 2, 1996. The staff has reviewed these changes and has. determined that you have adequately addressed ~six of the seven action items described in Section 5.0 of the May 2,1996, safety evaluation as discussed in the enclosure. The exception, Valve Relief Request VR-45-R1, was i not fully evaluated in the previous safety evaluation because of an error by the NRC staff. This relief request has now been reviewed as documented in the enclosed safety evaluation. In Valve Relief Request VR-45-R1, the licensee proposes to perform disassembly and inspection of the associated check valves

in lieu of the stroke testing required by the Code. As discussed in Section 3.7 of the staff's safety evaluation, the licensee's proposal to demonstrate valve operability by disassembling and inspecting the core spray pump minimum flow check valves is in accordance with the guidance of Generic Letter 89-04, Position 2. Therefore, relief is not required.

If you have any questions regarding this issue, please contact me at (301) 415-2828.

I Sincerely, MC M MIE3 COPY rigina signed by:

John N. Hannon, Director Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Enclosure:

As stated Docket No. 50-341 Jo\

y cc w/ encl: See next page DJSTRIBUTION:

Docket File: PD3-1 R/F BMcCabe 1 PUBLIC EAdensam (EGA1) OGC l

'ACRS MJordan, RIII JColaccino JRoe, GHill (2) (

DOCUMENT NAME: \ kFERMI\FE97306.RLF*See previous concurrence OFFICE PM:PD31 E LA:PD31 E *BC:EMEB E OGC,f /) l D:PD31l /

NAME A g r CJamerson D Fi h JHanno

[

DATE 02/g/97 02/t7/97 9 01/22/97 02/W/97 02/ V/97

0FFLCIAL RECORD COPY 9702250079 970219 PDR ADOCK 05000341 p PDR

p tM4

[  % UNITED STATES j j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001 o

• ..,+ February 19, 1997 t

Mr. Douglas R. Gipson Senior Vice President Nuclear Generation Detroit Edison Company

6400 North Dixie Highway Newport, Michigan 48166

SUBJECT:

FERMI 2 - SAFETY EVALUATION OF PORTIONS OF REVISION 3, CHANGE 11 TO THE PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. M97306)

Dear Mr. Gipson:

On November 1, 1996, you submitted Revision 3, Change 11 to the Fermi 2 pump and valve inservice testing program. Some of the changes included in this

, document were in response to an NRC staff safety evaluation of pump and valve relief requests dated May 2, 1996. The staff has reviewed these changes and i'

has determined that you have adequateiy addressed six of the seven action items described in Section 5.0 of the May 2, 1996, safety evaluation as discussed in the enclosure. The exception, Valve Relief Request VR-45-R1, was not fully evaluated in the previous safety evaluation because of an error by the NRC staff. This relief request has now been reviewed as documented in the enclosed safety evaluation. In Valve Relief Request VR-45-R1, the licensee proposes to perform disassembly and inspection of the associated check valves in lieu of the stroke testing required by the Code. As discussed in Section 3.7 of the staff's safety evaluation, the licensee's proposal to demonsi. rate valve operability by disassembling and inspecting the core spray pump minimum flow check valves is in accordance with the guidance of Generic Letter 89-04, Position 2. Therefore, relief is not required.

If you have any questions regarding this issue, please contact me at (301) 415-2828.

l Sincerely, John N. Hannon, Director Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Enclosure:

As stated Docket No. 50-341 cc w/ encl: See next page d

... - . . = . . . - - .. .- - . .. .. --

' ~

Mr. Douglas R. Gipson Fermi-2 Detroit Edison Company 1

i cc: '

a John Flynn, Esquire Senior Attorney Detroit Edison Company 2000 Second Avenue l 3 Detroit, Michigan 48226 '

Drinking Water and Radiological Protection Division l Michigan Department of Environmental Quality . l

! 3423 N. Martin Luther King Jr Blvd P. O. Box 30630 CPH Mailroom Lansing, Michigan 48909-8130 U.S. Nuclear Regulatory Commission Resident Inspector's Office i 6450 W. Dixie Highway .

Newport, Michigan 48166 Monroe County Emergency Management Division 1 963 South Raisinville Monroe, Michigan 48161 Regional Administrator, Region III

U.S. Nuclear Regulatory Commission -

801 Warrenville Road Lisle, Illinois 60532-4351 i Peter W. Smith j Director, Nuclear Licensing Detroit Edison Company

Fermi 270 TAC 6400 North Dixie Highway Newport, Michigan 48166

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