ML20206J913

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Forwards SE Finding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves,
ML20206J913
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 05/10/1999
From: Kugler A
NRC (Affiliation Not Assigned)
To: Gipson D
DETROIT EDISON CO.
Shared Package
ML20206J918 List:
References
GL-95-07, GL-95-7, TAC-M93463, NUDOCS 9905130016
Download: ML20206J913 (5)


Text

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y 10, 1999 Mr. Douglas R. Gipson S:nior Vice Pr:sident Nuclear Generation Detroit Edison Company 6400 North Dixie Highway

. Newport, MI 48166

SUBJECT:

COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-07,

" PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES," DATED AUGUST 17,1995 - FERMI-2 (TAC NO. M93463)

Dear Mr. Gipson:

On August 17,1995, the NRC issued Generic Letter (GL) 95-07," Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to request that licensees take actions to ensure that safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions.

In a letter dated February 13,1996, you submitted your 180-day response to GL 95-07 for Fermi 2. The NRC staff reviewed that submittal and requested additional information (RAl)in a letter dated July 8,1996. In a letter dated August 7,1996, you provided the additional information. The staff discussed a potential second RAI (Enclosure 1) with your staff on April 15,1999. Based on that discussion and further evaluation, the staff determined that the RAI was not necessary because the stated scenario.would not lead to pressure locking.

The staff has completed its review of your submittals and finds that you have adequately addressed the actions requested in GL 95-07. A copy of the staff's safety evaluation is provided in Enclosure 2. This completes the staff effort on this issue and closes T.eC No. M93463.

Sincerely, Original signed by:

Andrew J. Kugler, Project Manager, Section 1 Project Directorate lli Division of Licensing Project Management Office of Nuclear Reactor Regulation

\

Docket No. 50-341

Enclosures:

As stated ( l cc w/ encl: See next page DISTRIBUTION:

Docket File PUBLIC PD31 Rdg CThomas/GDick JZwolinski/SBlack AVegel, Rlll STingen OGC ACRS RCN DOCUMENT NAME: G:\PD3-1\WPDOCS\ FERMI \SE-93463.WPD Ta receive a cop r of this document, indicate in the box: *C" = Copy without attachment /endosure "E" = Copy with attachmengendosure "W = No copy OFFICE PM:LPD3 lE LA:LPD3 lE C:EMEB SC:LDFS ,, l NAME AKugler Ch)1 THarris M Elmbro @ GDick WK.gf.

DATE 05/4 /S8 V 05/9 /98 05/f/98 05//0 /98 '

OFFICIAL RECORD COPY

.4 3 nod "

9905130016 990510 i DR ADOCK 050003 1

May 10, 1999

.' Mr. Douglas R. Gipson Senior Vice President Nuclear Generation Detroit Edison Company 6400 North Dixie Highway Newport, MI 48166

SUBJECT:

COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-07,

" PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES," DATED AUGUST 17,1995 - FERMI-2 (TAC NO. M93463) '

Dear Mr. Gipson:

. On August 17,1995, the NRC issued Generic Letter (GL) 95-07, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to request that licensees take actions to ensure that safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions.

In a letter dated February 13,1996, you submitted your 180-day response to GL 95-07 for Fermi 2. The NRC staff reviewed that submittal and requested additional information (RAI) in a letter dated July 8,1996. In a letter dated August 7,1996, you provided the additional information. The staff discussed a potential second RAI (Enclosure 1) with your staff on April 15,1999. Bas 6 on that discussion and further evaluation, the staff determined that the RAI was not necessary because the stated scenario would not lead to pressure locking.

-The staff has completed its review of your submittals and finds that you have adequately addressed the actions requested in GL 95-07. A copy of the staff's safety evaluation is provided in Enclosure 2. This completes the staff effort on this issue and closes TAC No. M93463.

Sincerely, Original' signed by:

Andrew J. Kugler, Project Manager, Section 1 Project Directorate lli Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-341

Enclosures:

As stated cc w/ encl: See next page DISTRIBUTION:

Docket File PUBLIC PD31 Rdg CThomas/GDick JZwolinski/SBlack AVegel, Rlli STingen OGC ACRS RCN l DOCUMENT NAME: G:\PD3-1\WPDOCS\ FERMI \SE-93463.WPD Ta receive a oop i of thle docuspent, indicate in the box: *C's Copy without attachment / enclosure *g* a Copy Mth attachment / enclosure *N" a No copy OFFICE PM:LPD3 lE LA:LPD3 lE C:EMEB l SC:LDP3,, l NAME AKugler: (WL. THarris djk Elmbro EE GDick TfKA.

DATE 05/4 /98 V 05/ i /98 05/ 5 "/98 05//0 /98 OFFICIAL RECORD COPY

. nn:

p \ UNITED STATES

, ;r NUCLEAR REGULATORY COMMISSION WAsHNOTON, D.C. 20ess 00M

    • l

% May 10, 1999 Mf.h, uglas R. Gipson SeniorVice President j Nuclear Generation Detroit Edison Company ,

6400 North Dixie Highway l Newport, MI 48166

SUBJECT:

COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-07, 4

" PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED l POWER-OPERATED GATE VALVES," DATED AUGUST 17,1995 - FERMI-2 L

(TAC NO. M93463)

Dear Mr. Gipson:

On August 17,1995, the NRC lasued Generic Letter (GL) 95-07, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to request that licensees take actions to ensure that safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions.

In a letter dated February 13,1996, you submitted your 180-day response to GL 95-07 for Fermi 2. The NRC staff reviewed that submittal and requested additional information (RAl)in a letter dated July 8,1996. In a letter dated August 7,.1996, you provided the additional information. The staff discussed a potential second RAI (Enclosure 1) with your staff on April 15,1999. Based on that discussion and further evaluation, the staff determined that the RAI was not necessary because the stated scenario would not lead to pressure locking.

The staff has completed its review of your submittals and finds that you have adequately addressed the actions requested in GL 95-07. A copy of the staff's safety evaluation is provided in Enclosure 2. This completes the staff effort on this issue and closes TAC No. M93463.

Sincerely, Andrew J. Kugler, Project Manager, Section 1 Project Directorate lil Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-341

Enclosures:

As stated cc w/ encl: See next page

r Mr. Douglas R. Gipson Detroit Edison Company. Fermi 2 l l

l l

- cc: l l

John Flynn, Esquire SeniorAttorney i Detroit Edison Company '

2000 Second Avenue Detroit, Michigan 48226 '

l Drinking Water and Radiological Protection Division ..

Michigan Department of' i Environmental Quality I

~ 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 6450 W. Dixie Highway Newport, Michigan 48166 Monroe County Emergency Management Division-963 South Raisinville

. Monroe, Michigan 48161 Regional Administrator, Region 111 U.S. Nuclear Regulatory Commission

' 801 Warrenville 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 December 1998 r......_._-.~~..... - - _ . . ~ . , _ , _ , , . , . _ . ._

i

PROPOSED REQUEST FOR ADDITIONAL INFORMATION RELATED TO l GENERIC LETTER 95-07, " PRESSURE LOCKING AND THERMAL BINDING

. OF SAFETY-RELATED POWER-OPERATED GATE VALVES," FOR FERMI-2 (WITHDRAWN)

Your February 13,1996, submittal states that high pressure coolant injection (HPCI) turbine steam admission valves, E4150F001 and E4150F003, are not susceptible to pressure locking because steam application and orientation is such that steam will not condense in the bonnets  ;

and that pressure locking does not occur unless there is a non-compressible fluid in the bonnet.

The NRC considers that hydraulic induced pressure locking can occur if the fluid (compressible or non-compressible) in a bonnet is at a higher pressure than the surrounding piping. However, thermal induced pressure locking will not occur if there is a compressible fluid in the bonnet.

Explain if E4150F001 and E4150F003 are susceptible to hydraulic pressure locking during an event that results in a reduction in reactor pressure but reactor pressure remains high enough to operate the HPCI turbine. During this type of event, pressure in the bonnets of E4150F001 and E4150F003 could be higher than upstream and downstrearn pressure when the valves are required to open.

4 ENCLOSURE 1


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