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| | number = ML20206J913 | | | number = ML20206J913 |
| | issue date = 05/10/1999 | | | issue date = 05/10/1999 |
| | title = Forwards SE Finding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 950817 | | | title = Forwards SE Finding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, |
| | author name = Kugler A | | | author name = Kugler A |
| | author affiliation = NRC (Affiliation Not Assigned) | | | author affiliation = NRC (Affiliation Not Assigned) |
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| | contact person = | | | contact person = |
| | document report number = GL-95-07, GL-95-7, TAC-M93463, NUDOCS 9905130016 | | | document report number = GL-95-07, GL-95-7, TAC-M93463, NUDOCS 9905130016 |
| | | title reference date = 08-17-1995 |
| | package number = ML20206J918 | | | package number = ML20206J918 |
| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 5 | | | page count = 5 |
| | | project = TAC:M93463 |
| | | stage = Approval |
| }} | | }} |
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| 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. | | 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. | | In a {{letter dated|date=February 13, 1996|text=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|date=July 8, 1996|text=letter dated July 8,1996}}. In a {{letter dated|date=August 7, 1996|text=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. | | 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: | | Sincerely, Original signed by: |
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| ==Dear Mr. Gipson:== | | ==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. | | . 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. | | In a {{letter dated|date=February 13, 1996|text=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|date=July 8, 1996|text=letter dated July 8,1996}}. In a {{letter dated|date=August 7, 1996|text=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. | | -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: | | Sincerely, Original' signed by: |
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| 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. | | 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. | | In a {{letter dated|date=February 13, 1996|text=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|date=July 8, 1996|text=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. | | 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 | | 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 |
Letter Sequence Approval |
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MONTHYEARML20206J9131999-05-10010 May 1999 Forwards SE Finding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Project stage: Approval 1999-05-10
[Table View] |
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Historical Listing of Plant Issues Encl IR 05000341/19990131999-08-19019 August 1999 Discusses Insp Rept 50-341/99-13 & OI Rept 3-98-039 Conducted Into Potential Misconduct of Operator Formerly Employed by De.Nrc Determined That Violation of NRC Regulations Occurred.Synopsis of IO Rept Encl ML20211C0521999-08-17017 August 1999 Forwards Tables for Sections 3.6 & 3.7 of Draft Safety Evaluation of Proposed Conversion of Current TS to Improved Standard TS IR 05000341/19990011999-08-10010 August 1999 Forwards Insp Rept 50-341/99-01 on 990619-0723 & Nov. Violation of Concern Because Operators Did Not Understand License Requirements & Placed Plant in Configuration Where EDG 11 Was Removed from Service IR 05000341/19990121999-08-0606 August 1999 Forwards Insp Rept 50-341/99-12 on 990712-0716.No Violations Noted.Insp Focused on Implementation of Plant Chemistry & Radiological Environ Monitoring Programs & Operation of post-accident Sampling Sys ML20211C4761999-08-0606 August 1999 Forwards Draft Safety Evaluation Re Proposed Conversion of Current TS to Improved Standard TS ML20210J2121999-07-23023 July 1999 Discusses NRC OI Investigation Rept 3-98-039 Completed on 990524 & Forwards Notice of Violation ML20209F6571999-07-12012 July 1999 Forwards Insp Rept 50-341/99-09 on 990516-0618.No Violations Noted.Weak Procedural Guidance,Communications Issues & Configuration Control Weaknessess Were Evident ML20196J5511999-07-0202 July 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & DE Responses & 980729 for Fermi 2.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 as Result of Review of Responses ML20209E9991999-06-30030 June 1999 Forwards Insp Rept 50-016/99-01 on 990614-17.No Violations Noted.Potential Weakness in Airborne Effluent Concentration Assessment Identified ML20209B2471999-06-29029 June 1999 Informs That NRR Revised Schedule for Conversion of Fermi 2 TS to Improved Std Ts.Planned Amend Date Has Been Moved to 990930 & Date for Draft Amend Has Been Moved to 990806 ML20207E4961999-06-0101 June 1999 Forwards Insp Rept 50-341/99-07 on 990402-0515.One Violation of NRC Requirements Occurred Re Failure to Keep TS Requirements Re Approval of Overtime Deviations.Violations Being Treated as non-cited Violations,Consistent with App C ML20207D3311999-05-26026 May 1999 Forwards Insp Rept 50-341/99-04 on 990503-07.No Violations Noted.During Insp,Nrc Observation of Licensee Activities Showed Radiological Emergency Response Preparedness Program Maintained in Effective State of Operational Readiness ML20206N7351999-05-14014 May 1999 Forwards RAI Re Plant Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During DBA Conditions ML20206N4621999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created. Reorganization Chart Encl ML20206J9131999-05-10010 May 1999 Forwards SE Finding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, ML20206Q7041999-05-0606 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-341/99-02 on 990308 ML20206G4931999-05-0505 May 1999 Refers to DE 980804 Requests for Relief (PR-8,Rev 2 & PR-12) from IST Requirements of ASME Code for RHR Pumps.Review of Relief Requests Completed.Se Approving Relief Requests Encl ML20206K4031999-04-29029 April 1999 Forwards Partially Withheld (Ref 10CFR73.21) Insp Rept 50-341/99-08 on 990405-09.No Violations Noted.Concern Expressed Over NRC Observations of Poor Performance Demonstrated During Some Contingency Response Drills ML20205T3841999-04-23023 April 1999 Forwards Insp Rept 50-341/99-03 on 990218-0401.Two Violations Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205S8481999-04-20020 April 1999 Informs That Changes in Rev 22 Do Not Decrease Effectiveness of Emergency Plan & Plan Continues to Meet Stds of 10CFR50.47(b) & Requirements of App E to 10CFR50.NRC Approval Is Not Required ML20205Q7001999-04-15015 April 1999 Forwards Amend 16 to License DPR-9,allowing Possession of Nominal Amount of Special Nuclear Matl,In Response to 980717 Application.Related SER & Notice of Issuance Also Encl ML20205P1691999-04-14014 April 1999 Forwards Insp Rept 50-341/99-06 on 990315-19.No Violations Noted.Insp Focused on Aspects of Radioactive Effluent Monitoring,Liquid Waste Processing,Esf Filtration & CR Habitability & Solid Waste Mgt & Transportation Programs ML20204E4061999-03-19019 March 1999 Forwards Insp Rept 50-341/99-05 on 990308-11.No Violations Noted.Insp Concluded That Fire Protection Program Was Effective ML20204E0271999-03-17017 March 1999 Forwards SE Accepting Licensee & Suppl, ,which Requested NRC Approval of Alternative Rv Weld Exam,Per 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5), for Plant,Unit 2 for 40-month Period ML20207L7281999-03-0909 March 1999 Informs That Util Ltrs & 981026 Responding to GL 96-01, Testing of Safety-Related Logic Circuits, Completes Licensing Action for Fermi 2 ML20207J1401999-03-0808 March 1999 Forwards Insp Rept 50-341/99-02 on 990111-29 & Notice of Violation.One Violation Identified in Area of Design Control.Violation of Concern Because Errors Existed in Three of Six Calculations Reviewed ML20207G5711999-03-0404 March 1999 Discusses 990301 Meeting Between GL Shear,M Mitchell, D Williams,C Budnik & M Clements Re Current Status of Radiation Protection Program at Facility ML20207E2491999-02-22022 February 1999 Discusses Licensee 980617 Updated Response to GL 96-05 Indicating Intent to Implement Provisions of JOG Program for MOV Periodic Verification for Fermi-2.Forwards RAI Re Fermi-2 Response to GL 96-05 ML20207E6451999-02-22022 February 1999 Submits Correction to Insp Rept 50-341/98-15 Issued on 981207.Rept Incorrectly Documented That Loose Internal Sleeving on Turbine Control Valve Caused Power Oscillations Greater than 10% During Plant Operation ML20203F6761999-02-11011 February 1999 Forwards Request for Addl Info Re Conversion to Improved Standard Ts,Section 3.6 for Fermi 2 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203F6911999-02-10010 February 1999 Discusses Completion of Licensing Action for Bulletin 96-03, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors, ML20203G6411999-02-0808 February 1999 Informs of Receipt of Encl FEMA Correspondence Received 990119,transmitting FEMA Final Exercise Rept for 980608 Plume Exposure Pathway Exercise at Enrico Fermi II Npp.No Deficiencies Were Identified During Exercise ML20202H8881999-02-0404 February 1999 Clarifies Intent of RAI Re Plant Staff Qualifications & Reg Guide 1.8,Rev 2, Qualification & Training of Personnel for Nuclear Power Plants, Dtd Apr 1987.Staff Position on Issue Neither New Nor Different Position from Previous Position ML20202H6111999-01-25025 January 1999 Requests Addl Info Re Conversion to Improved Std Tss, Section 3.5 for Fermi 2 ML20206S1111999-01-21021 January 1999 Forwards Insp Rept 50-341/98-19 on 981110-990104.No Violations Noted.Inspectors Noted Potential Trend Re Documented Operability Assessments That May Not Have Been Performed for C/A Resolution Documents ML20199G7561999-01-14014 January 1999 Forwards Request for Addl Info Re Conversion to Improved Stds Tss,Section 3.3 for Plant ML20198S3101999-01-0606 January 1999 Forwards Amend 15 to License DPR-9,consisting of Changes to TS in Response to 980128 Application.Related SER & Notice of Issuance,Also Encl 1999-09-09
[Table view] |
Text
_--_________-__ - -__ __
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
% 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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