ML20206N735

Forwards RAI Re Plant Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During DBA Conditions

ML20206N735
Person / Time
Site:	Fermi
Issue date:	05/14/1999
From:	Kugler A NRC (Affiliation Not Assigned)
To:	Gipson D DETROIT EDISON CO.
References
GL-96-06, GL-96-6, TAC-M96811, NUDOCS 9905180047
Download: ML20206N735 (5)

Text

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, ,Mr. Douglis R. Gipson Flay 14,1999 i S2nior Vice Prcsident Nuclear Generation Detroit Edison Company 6400 North Dixie Highway Newport, MI 48166

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE FERMI-2 RESPONSE TO GENERIC LETTER 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS," (TAC NO. M96811)

Dear Mr. Gipson:

The NRC issued Generic Letter (GL) 96-06 on September 30,1996, to request that nuclear power plant licensees submit certain information relative to water hammer, two-phase flow, and thermally induced overpressurization in lines penetrating containment and to implement actions, as appropriate, to address these issues. You provided responses to the GL and to requests for additional information in letters dated October 30,1996, January 28 and October 17,1997, and June 30,1998.

Additional information, as discussed in the enclosure, is requested in order for the staff to complete its review. The enclosed request was discussed with Mr. R. Johnson of your staff on 4 May 13,1999. A mutually agreeable completion schedule of 30 days was established. If I circumstances result in the need to revise the schedule, please call me at the earliest opportunity, if you have any questions conceming this request, please contact me at (301) 415-2828.

Sincerely, Original signed by:

Andrew J. Kugler, Project Manager, Section 1

- Project Directorate lil Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-341'-

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Enclosure:

As stated cc w/ encl: See'next page

? S ()/;g . l DISTRIBUTION:

AVegel, Rill BJain SEDB- ACRS SBlack fdf Docket File PUBLIC PD3-ir/f OGC  :

DOCUMENT NAME: G:\PD3-1\WPDOCS\ FERMI \RAl96811.WPD To recehre a cessy of this docuenent, Indicate in the box: "C" a Copy unthout altammenvenclosure T = Copy with attachment / enclosure "N" a No copy OFFICE PM:LPD3 lE LA:LPD3 lE (A)SC:LfDh lE NAME AKugler: QM./ THarrisJ& GDick M/

DATE 05/ f 4 /99 U 05/ny /99 05//4- /994 OFFICIAL RECORD COPY

( :9905180047 990514 i PDR ADOCK 05000341 P PM j

Mr. Dougins R. Gipson

, Senior Vice Prssident g,y 14, 1999 ri . Nucirr G:;nertti:n Detroit Edison Company 6400 North Dixie Highway Newport, MI 48166

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE FERMI-2 RESPONSE TO GENERIC LETTER 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS," (TAC NO. M96811)

Dear Mr. Gipson:

The NRC issued Generic Letter (GL) 96-06 on September 30,1996, to request that nuclear power plant licensees submit certain information relative to water hammer, two-phase flow, and thermally induced overpressurization in lines penetrating containment and to impbment actions, as appropriate, to address these issues. You provided responses to the GL and to requests for additional information in letters dated October 30,1996, January 28 and October 17,1997, and June 30,1998.

Additional information, as discussed in the enclosure, is requested in order for the staff to complete its review. The enclosed request was discussed with Mr. R. Johnson of your staff on May 13,1999. A mutually agreeable completion schedule of 30 days was established. If circumstances result in the need to revise the schedule, please call me at the earliest opportunity.

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

Sincerely, Original signed by: )

Andrew J. Kugler, Project Manager, Section 1 Project Directorate lll Division of Licensing Project Management j

Office of Nuclear Reactor Regulation Docket No. 50-341

Enclosure:

As stated cc w/ encl: See next page  ;

i DISTRIBUTION.  ;

AVegel, Rlli BJain SEDB- ACRS SBlack i Docket File PUBLIC PD3-ir/f OGC  !

DOCUMENT NAME: G:\PD3-1\WPDOCS\ FERMI \RAl96811 WPD To receive a copy of this document, ind6cato in the %es: "C" = Copy wnhout sRechment/ enclosure T = Copy weh attachment / enclosure "tr's No copy OFFICE PM:LPD3 lE LA:LPD3 lE (A)SC:Li(D) lE l NAME AKugler. Q,hC/ THarrisJAF GDick M/ {

DATE 05/14 /99 V 05/M /99 05/ /4- /99

• OFFICIAL RECORD COPY

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} NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20046 0001

'+4***** May 14, 1999 Mr. Douglas R. Gipson Senior Vice President Nuclear Generation Detroit Edison Company 6400 North Dixie Highway Newport, MI 48166

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE FERMI-2 RESPONSE TO GENERIC LETTER 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS," (TAC NO. M96811)

Dear Mr. Gipson:

The NRC issued Generic Letter (GL) 96-06 on September 30,1996, to request that nuclear power plant licensees submit certain information relative to water hammer, two-phase flow, and thermally induced overpressurization in lines penetrating containment and to implement actions, as appropriate, to address these issues. You provided responses to the GL and to requests for additional information in letters dated October 30,1996, January 28 and October 17,1997, and June 30,1998.

Additional information, as discussed in the enclosure, is requested in order for the staff to complete its review. The enclosed request was discussed with Mr. R. Johnson of your staff on May 13,1999. A mutually agreeable completion schedule of 30 days was established. If circumstances result in the need to revise the schedule, please call me at the earliest opportunity.

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

Sincerely,

/

Andrew . Kug r, Project Manager, Section 1 Project Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-341

Enclosure:

As stated cc w/ encl: See next page I

4 * 'Q .

Mr. Douglas R. Gipson Detroit Edison Company Fermi 2 cc:

John Flynn, Esquire SeniorAttorney Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Drinking Water and Radiological .

Protection Division Michigan Department of Environmental Quality 3423 N. Martin Luther Ksng Jr Blvd P. O. Box 30630 CPH Mailroom Lansing, Michigan 48909-8130 U.S. Nuclear Regulatory Commission Resident inspector's Office 6450 W. Dixie Highway Newport, Michigan 48166 Monroe County Emergency Management L Division l 963 South Raisinville '

Monroe, Michigan 48161 Regional Administrator, Region ill U.S. Nuclear Regulatory Commission 801 Wavenville Road Lisle, Illinois 60532-4351 Norman K. Peterson Director, Nuclear Licensing Detroit Edison Company Fermi 2 -280 TAC 6400 North Dixie Highway Newport, Michigan 48166 Decembw 1998

_7.~ _ . . _

,9 5 ,

REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE FERMI-2 RESPONSE TO GENERIC LETTER 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS,"(TAC NO. M96811)

1. In your submittal dated March 27,1998, in response to Generic Letter 96-06, you stated that modifications were not planned for three (X-8, X-49a,and X-51a) of the six drywell penetrations that were, identified as susceptible to thermally induced pressurization. You determined that modifications were not necessary on the basis that these penetrations )

satisfy the strain criteria as proposed in the Electric Power Research Institute (EPRI) Report TR-108912R1. However, the staff has provided several comments to the industry on the proposed criteria and the EPRI strain criteria is not acceptable to the staff. You need to re-evaluate these three penetrations and consider installing relief devices or some other means to protect the penetrations from thermally induced pressurization. Provide the schedule for your evaluation.

2. For Psnetration X-29Aa, provide the calculation that shows that the pressure acting under the inboard isolation valve seat will open the spring-to-close isolation valve to relieve the pressure, and discuss any source of uncertainty associated with the calculated lift pressure.

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3. For penetrations X-18 and X-19, confirm whether the rupture disks have been installed and I how you have assured that these pressure relief mechanisms will function as intended.

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ENCLOSURE I

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