NRC-96-0122, Forwards Rev 3,Change 11 to Inservice Testing Program (Plan) for Pumps & Valves for Fermi 2 Power Plant

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Forwards Rev 3,Change 11 to Inservice Testing Program (Plan) for Pumps & Valves for Fermi 2 Power Plant
ML20129J032
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 11/01/1996
From: Gipson D
DETROIT EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20129J034 List:
References
CON-NRC-96-0122, CON-NRC-96-122 NUDOCS 9611060110
Download: ML20129J032 (2)


Text

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. Dougi2s R. Gipson Senor Vce President Nuclear Genersten j

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Fermi 2 6400 North Dune Hghway Newport, Mchigan 48166 l

(313) 586 6249 l

November 1,1996 NRC-96-0122 U. S. Nuclear Regulatory Commission 3

Attn: Document Control Desk Washington, D. C. 20555

References:

1)

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

NRC Inspection Report 50-341/95002, dated February 10,1995_

)

3)

Detroit Edison Letter NRC-95-0076 - Transmittal of the i

Detroit Edison Inservice Testing Program (Plan) For Pumps And Valves, Revision 3, Change 9, dated July 19,1996 l

4)

NRC Letter - Safety Evaluation of Pump and Valve Relief Requests For The Pump And Valve Inservice Testing Program, dated May 2,1996 l

Subject:

Inservice Testing Program (Plan) For Pumps And Valves l

Revision 3. Change 11 l

l Please find attached Revision 3, Change 11 of the Inservice Testing Program (Plan) for pumps and valves, Change 11 to the Inservice Testing (IST) Plan is being sent to confirm actions taken by Detroit Edison in response to the Safety Evaluation issued f

on May 2,1996 (Reference 4).

/

The Safety Evaluation, references two items which required further discussion

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between Detroit Edison and the NRC. The Safety Evaluation stated that Detroit l

Edison should partial-stroke test the Core Spray pump discharge check valves after g

reassembly. These valves are currently in the IST program for disassembly /

961106011o 961101 POR ADOCK 05000341 P

ppe

USNRC l

November 1,1996 l

i NRC-96-0122 l

Page 2 i

l inspection and partial stroke testing. The relief request VR - 45 which was submitted -

l by Reference 3 and evaluated by NRC Safety Evaluation (Reference 4) is for the Core l

l.

Spray pump minimum flow check valves not the Core Spray discharge check valves.

The minimum flow check valves cannot be partial stroke tested due to valve configuration, and the design of the Core Spray system where two pumps are operated in parallel under accident and testing conditions. This discrepancy between i

the Safety Evaluation and Relief Request was discussed during a conference call on i

September 12,1996.

l The Safety Evaluation also stated the current IST program is based on the i

requirements of the 1980 Edition through the winter 1981 addenda of the American i

Society of Mechanical Engineers (ASME) Code. Detroit Edison is currently j

committed to the 1980 Edition through the winter 1980 Addenda of the ASME Code l

as identified in Supplement 4 of the Fermi 2 Safety Evaluation Report. These two items were discussed with Messrs. Colaccino and Kugler of the NRC on September 12,1996.

l Ifyou have any questions please contact Mr. Bmce. J.Sheffel at (313) 586-1848, f

l 1

I i

Sincerely,

]

r I

l Attachment l

cc: A. B. Beach J. Colaccino w/ encl.

M. J. Jordan

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A. J. Kugler w/ encl.

A. Vegel i

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