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MONTHYEARML20206A4851999-04-26026 April 1999 Informs That Staff Needs to Conduct Phone Call with Licensee on Licensee Response to GL 95-07.In Order to Conduct Phone Call,Staff Needs to Provide Licensee with Attached Info Project stage: Other 1999-04-26
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217D7031999-10-0707 October 1999 Informs That USNRC Had Dicussions with Licensee on 990908 Application for License Amend to Relocate 18-month Standby Diesel Generator Insp Sr.Forwards Preliminary Info Submitted by Licensee Re Supplement to Application ML20212L3481999-10-0101 October 1999 Forwards Document Re Replacement SG Water Level Trip Setpoint Differences to Be Placed in PDR ML20216F9021999-09-21021 September 1999 Notification of 991005-07 Meeting with STP Nuclear Operating Co in Bay City,Tx,To Review Plant Categorization & Feedback Process of Risk Ranking Components ML20211J2141999-08-27027 August 1999 Notification of 990831 Meeting with Util to Discuss Issues Associated with STPNOC Recent Request to Exclude safety- Related Low Risk Significant & non-risk Significant Components from Scope of Special Treatment Requirements ML20211G7001999-08-25025 August 1999 Forwards Examination Rept with as Given Written Exam Administered on 990706-15 for Distribution Under Rids Code IE42 ML20211G2501999-08-25025 August 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990706-15 ML20211F3801999-08-20020 August 1999 Notification of 990831 Meeting with Util in Rockville,Md to Discuss Issues Associated with STPNOC Recent Request to Exclude safety-related low-risk Significant & non-risk Significant Components, Designated Under Gqa Program ML20210P9351999-08-0909 August 1999 Notification of 990923 Meeting with Util in Arlington,Tx to Introduce New Director,Safety Quality Concerns Program & Status of Activities to Support Confirmatory Order Modifying License ML20210M6841999-08-0505 August 1999 Notification of Licensee Meeting with Util on 990914 in Arlington,Tx to Discuss New Mgt Team Introduction & Site Status ML20209D5751999-07-0909 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Licensee Proposed SG Water Level Trip Setpoint TS & Setpoint Impact on Pressurizer Water Level TS Per 10CFR50.36 ML20196L1481999-07-0707 July 1999 Forwards Info Provided by Licensee to Facilitate Conference Calls Re Licensee Desire to Propose Emergency Technical Specification Changes on Fuel Handling Building Exhaust Air Sys ML20212J2641999-06-24024 June 1999 Forwards Addl Info from Licensee Re Clarification of Sentence in Util (on Page 4 of 7) Which States That, Isolation Valves in This Sys Designed to Be Operated remote-manually from Control Room ML20195J0441999-06-14014 June 1999 Refers to Discussions with Licensee on Future Suppl to Application on Replacement Steam Generator Reactor Coolant Flow Differences ML20195J0841999-06-14014 June 1999 Forwards Info Re Suppl to Application on TS 3.6.3,action B, to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration,To Be Placed in PDR ML20207E8961999-06-0303 June 1999 Discusses Which Submitted Relief Request RR-ENG-2-8 Which Requested Relief from ASME Code Based on Provisions of Code Case N-491-2.Requests That Encl Be Placed Into PDR ML20207D9911999-05-28028 May 1999 Informs That NRC Requested That Licensees Respond to Survey on Hydrogen Storage Facilities,To Support Preliminary Evaluation to Determine If Addl Study Warranted.South Texas Project Licensee Response Encl for Placement in PDR ML20207A6671999-05-20020 May 1999 Notification of 990602 & 03 Meeting with Util in South Texas Project Nuclear Support Ctr,Southwest of Bay City,Tx,In Order for Licensee to Present low-power Shutdown Risk Model ML20207A3381999-05-19019 May 1999 Informs of Discussions with Licensee on 980831 Application for License Amend to TS 3.4.9.3 to Reflect Revised Cold Overpressure Mitigation Curve Associated with Replacement Sgs.Request That Encl Documents Be Placed in PDR ML20206N6411999-05-13013 May 1999 Refers to Discussions with Licensee on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20206G5041999-05-0404 May 1999 Requests That Enclosures 1 & 2 Re 990412 Conference Call, Discussing Preliminary Results of SG Insp,Be Placed in PDR ML20206G2041999-05-0404 May 1999 Discusses 981201 Telcon Between NRC Staff & STP Re 10CFR50.59 Evaluation of MSLB Reanalysis & Effect on Isolation Valve Cubicle & Rcb.Requests That Encl Draft Info Be Placed in PDR ML20206A4851999-04-26026 April 1999 Informs That Staff Needs to Conduct Phone Call with Licensee on Licensee Response to GL 95-07.In Order to Conduct Phone Call,Staff Needs to Provide Licensee with Attached Info ML20205Q8251999-04-15015 April 1999 Forwards Documentation on Licensee 980928 Proposed Changes to TS on Control Room & Fuel Handling Bldg Ventilation Sys, Per 990304 Discussion with Util ML20205Q7961999-04-15015 April 1999 Forwards Documentation from Preliminary Discussions with Licensee on Proposed Changes to Atmospheric Steam Relief Valve Tss.Licensee Subsequently Made Formal Application on 990322 (Accession Number 9903300195) ML20205Q8111999-04-15015 April 1999 Forwards Draft Undated Rev 6 to Operations QA Plan Independent Technical Review, Per Discussions with Licensee on 990407 Re Proposed Change to TSs on Independent Safety Engineering Group ML20204H7731999-03-22022 March 1999 Notification of Significant Licensee Meeting with Util on 990419 in Arlington,Tx to Present Overview of Licensee Emergency Plan ML20207G8201999-03-0404 March 1999 Notification of Significant Licensee Meeting with Util on 990325 to Discuss Plant Performance Review Results ML20207K2301999-03-0404 March 1999 Notification of 990315 Meeting with STP Nuclear Operating Co in Rockville,Md So Licensee May Present risk-informed Exemptions Util Need for Implementation of Graded Quality Assurance at South Texas Project ML20199D1891999-01-11011 January 1999 Notification of 990126 Meeting with STP Nuclear Operating Co to Discuss C/As for Incomplete Control Rod Insertion Anomaly & to Discuss Need for Future mid-cycle Control Rod Drop Testing ML20198H3281998-12-15015 December 1998 Forwards Draft Info Submitted by Util Re 980728 Application for Amend Concerning Operator Action to Mitigate Sbloca,Per 981117 Telcon & for Placement in PDR ML20196G1521998-12-0303 December 1998 Forwards Draft Outline to NRC to Facilitate Discussions Between Util & NRC Re Actions Believed Needed to Address Restraints to Implementation of Graded QA ML20196F1751998-11-27027 November 1998 Notification of Licensee Meeting with Util on 981210 in Arlington,Tx to Discuss Certain Issues of Comprehensive Cultural Assessment for South Texas Project Site ML20196A8641998-11-24024 November 1998 Notification of 981208 Meeting with Util in Rockville,Md to Discuss Status of Current & Proposed Licensing Actions & Activities for Plant ML20195B9251998-11-10010 November 1998 Forwards,For Placement in Pdr,Draft Proposals That Were Provided by Licensee at Request of Staff,In Order to Assist Staff in Developing Commission Paper on Options for Making 10CFR50 More risk-informed ML20155H7471998-11-0505 November 1998 Notification of 981117 Meeting with STP Nuclear Operating Co in Arlington,Tx Re Presentation by Rosen,Manager,Risk Mgt& Industrial Relations on Licensee Perspective on Probablistic Risk Analysis ML20155C2651998-10-29029 October 1998 Forwards SG Insp Results Conducted in Oct 1998,to Be Placed in Pdr.Licensee Provided Info to Facilitate 981015 Conference Call ML20155C2231998-10-29029 October 1998 Forwards Draft Ltr from STP Nuclear Operating Co on Action Needed for Implementation of Graded QA for Plant Units 1 & 2 for Placement in PDR ML20155C2171998-10-26026 October 1998 Notification of 981109-10 Meeting with Util to Obtain Info from Licensee for NRC Proposed risk-informed Insp & Assessment Program.Agenda Encl ML20154L4101998-10-0909 October 1998 Forwards NRC Operator Licensing Exam Repts 50-498/98-301 & 50-499/98-301,including Completed Graded Tests Administered on 980602-04 ML20154L9261998-10-0909 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980602-04 ML20154A0331998-09-24024 September 1998 Informs That Based on Review of Licensee 10CFR50.59 Evaluation of Environ Qualification of Mechanical Components,Staff Found That Proposed Change to UFSAR to Eliminate Meq Program Would Not Alter Any Plant Sys ML20151Y7231998-09-12012 September 1998 Notification of Licensee Meeting with Util on 981013 in Arlington,Tx Re Licensee Presentation Concerning Graded Quality Assurance Program at Plant ML20239A0941998-09-0303 September 1998 Notification of 980915 Meeting W/Util in Rockville,Md to Discuss Problems W/Implementing Graded QA,10CFR50.59,impact on risk-informed Applications & Comments on NRC Proposed Rev to 10CFR50.59 ML20239A1171998-09-0202 September 1998 Notification of 980915 Meeting W/Stp Nuclear Operating Co in Rockville,Md Re Licensee Presentation of Uses of Probabilistic Safety Assessment ML20151T6061998-09-0101 September 1998 Notification of Significant Licensee Meeting W/Util on 980918 to Discuss Licensee Insp Plans for Units 1 & 2 Replacement Steam Generators ML20236X8171998-08-0303 August 1998 Notification of Licensee Meeting W/Util on 980820 in Arlington,Tx to Discuss Certain Issues Ongoing at STP Site ML20249A6781998-06-16016 June 1998 Forwards Confirmatory Order Modifying Licenses NPF-76 & NPF-80 (Effective Immediately),For Transmittal to Ofc of Fr for Publication.W/O Encl ML20216J4491998-04-16016 April 1998 Notification of 980506 Meeting W/Util in Rockville,Md to Discuss Proposed Merger Between Aep & Central Southwest ML20217K9381998-04-0303 April 1998 Notification of 980413 Meeting W/Util in Rockville,Md to Discuss Licensee Desire for Update on Schedule for NRC Review of Licensee Application for Conversion to Improved Std TSs ML20197B0551998-03-0505 March 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam submittal,2nd & 3rd Exam Submittal as Given Operating Exam Administered on 971020-1205 1999-09-21
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217D7031999-10-0707 October 1999 Informs That USNRC Had Dicussions with Licensee on 990908 Application for License Amend to Relocate 18-month Standby Diesel Generator Insp Sr.Forwards Preliminary Info Submitted by Licensee Re Supplement to Application ML20212L3481999-10-0101 October 1999 Forwards Document Re Replacement SG Water Level Trip Setpoint Differences to Be Placed in PDR ML20216F9021999-09-21021 September 1999 Notification of 991005-07 Meeting with STP Nuclear Operating Co in Bay City,Tx,To Review Plant Categorization & Feedback Process of Risk Ranking Components ML20211J2141999-08-27027 August 1999 Notification of 990831 Meeting with Util to Discuss Issues Associated with STPNOC Recent Request to Exclude safety- Related Low Risk Significant & non-risk Significant Components from Scope of Special Treatment Requirements ML20211G2501999-08-25025 August 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990706-15 ML20211G7001999-08-25025 August 1999 Forwards Examination Rept with as Given Written Exam Administered on 990706-15 for Distribution Under Rids Code IE42 ML20211F3801999-08-20020 August 1999 Notification of 990831 Meeting with Util in Rockville,Md to Discuss Issues Associated with STPNOC Recent Request to Exclude safety-related low-risk Significant & non-risk Significant Components, Designated Under Gqa Program ML20210P9351999-08-0909 August 1999 Notification of 990923 Meeting with Util in Arlington,Tx to Introduce New Director,Safety Quality Concerns Program & Status of Activities to Support Confirmatory Order Modifying License ML20210M6841999-08-0505 August 1999 Notification of Licensee Meeting with Util on 990914 in Arlington,Tx to Discuss New Mgt Team Introduction & Site Status ML20209D5751999-07-0909 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Licensee Proposed SG Water Level Trip Setpoint TS & Setpoint Impact on Pressurizer Water Level TS Per 10CFR50.36 ML20196L1481999-07-0707 July 1999 Forwards Info Provided by Licensee to Facilitate Conference Calls Re Licensee Desire to Propose Emergency Technical Specification Changes on Fuel Handling Building Exhaust Air Sys ML20212J2641999-06-24024 June 1999 Forwards Addl Info from Licensee Re Clarification of Sentence in Util (on Page 4 of 7) Which States That, Isolation Valves in This Sys Designed to Be Operated remote-manually from Control Room ML20195J0841999-06-14014 June 1999 Forwards Info Re Suppl to Application on TS 3.6.3,action B, to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration,To Be Placed in PDR ML20195J0441999-06-14014 June 1999 Refers to Discussions with Licensee on Future Suppl to Application on Replacement Steam Generator Reactor Coolant Flow Differences ML20207E8961999-06-0303 June 1999 Discusses Which Submitted Relief Request RR-ENG-2-8 Which Requested Relief from ASME Code Based on Provisions of Code Case N-491-2.Requests That Encl Be Placed Into PDR ML20207D9911999-05-28028 May 1999 Informs That NRC Requested That Licensees Respond to Survey on Hydrogen Storage Facilities,To Support Preliminary Evaluation to Determine If Addl Study Warranted.South Texas Project Licensee Response Encl for Placement in PDR ML20207A6671999-05-20020 May 1999 Notification of 990602 & 03 Meeting with Util in South Texas Project Nuclear Support Ctr,Southwest of Bay City,Tx,In Order for Licensee to Present low-power Shutdown Risk Model ML20207A3381999-05-19019 May 1999 Informs of Discussions with Licensee on 980831 Application for License Amend to TS 3.4.9.3 to Reflect Revised Cold Overpressure Mitigation Curve Associated with Replacement Sgs.Request That Encl Documents Be Placed in PDR ML20206N6411999-05-13013 May 1999 Refers to Discussions with Licensee on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20206G2041999-05-0404 May 1999 Discusses 981201 Telcon Between NRC Staff & STP Re 10CFR50.59 Evaluation of MSLB Reanalysis & Effect on Isolation Valve Cubicle & Rcb.Requests That Encl Draft Info Be Placed in PDR ML20206G5041999-05-0404 May 1999 Requests That Enclosures 1 & 2 Re 990412 Conference Call, Discussing Preliminary Results of SG Insp,Be Placed in PDR ML20206A4851999-04-26026 April 1999 Informs That Staff Needs to Conduct Phone Call with Licensee on Licensee Response to GL 95-07.In Order to Conduct Phone Call,Staff Needs to Provide Licensee with Attached Info ML20205Q8251999-04-15015 April 1999 Forwards Documentation on Licensee 980928 Proposed Changes to TS on Control Room & Fuel Handling Bldg Ventilation Sys, Per 990304 Discussion with Util ML20205Q8111999-04-15015 April 1999 Forwards Draft Undated Rev 6 to Operations QA Plan Independent Technical Review, Per Discussions with Licensee on 990407 Re Proposed Change to TSs on Independent Safety Engineering Group ML20205Q7961999-04-15015 April 1999 Forwards Documentation from Preliminary Discussions with Licensee on Proposed Changes to Atmospheric Steam Relief Valve Tss.Licensee Subsequently Made Formal Application on 990322 (Accession Number 9903300195) ML20204H7731999-03-22022 March 1999 Notification of Significant Licensee Meeting with Util on 990419 in Arlington,Tx to Present Overview of Licensee Emergency Plan ML20207G8201999-03-0404 March 1999 Notification of Significant Licensee Meeting with Util on 990325 to Discuss Plant Performance Review Results ML20207K2301999-03-0404 March 1999 Notification of 990315 Meeting with STP Nuclear Operating Co in Rockville,Md So Licensee May Present risk-informed Exemptions Util Need for Implementation of Graded Quality Assurance at South Texas Project ML20199D1891999-01-11011 January 1999 Notification of 990126 Meeting with STP Nuclear Operating Co to Discuss C/As for Incomplete Control Rod Insertion Anomaly & to Discuss Need for Future mid-cycle Control Rod Drop Testing ML20198H3281998-12-15015 December 1998 Forwards Draft Info Submitted by Util Re 980728 Application for Amend Concerning Operator Action to Mitigate Sbloca,Per 981117 Telcon & for Placement in PDR ML20196G1521998-12-0303 December 1998 Forwards Draft Outline to NRC to Facilitate Discussions Between Util & NRC Re Actions Believed Needed to Address Restraints to Implementation of Graded QA ML20196F1751998-11-27027 November 1998 Notification of Licensee Meeting with Util on 981210 in Arlington,Tx to Discuss Certain Issues of Comprehensive Cultural Assessment for South Texas Project Site ML20196A8641998-11-24024 November 1998 Notification of 981208 Meeting with Util in Rockville,Md to Discuss Status of Current & Proposed Licensing Actions & Activities for Plant ML20195B9251998-11-10010 November 1998 Forwards,For Placement in Pdr,Draft Proposals That Were Provided by Licensee at Request of Staff,In Order to Assist Staff in Developing Commission Paper on Options for Making 10CFR50 More risk-informed ML20155H7471998-11-0505 November 1998 Notification of 981117 Meeting with STP Nuclear Operating Co in Arlington,Tx Re Presentation by Rosen,Manager,Risk Mgt& Industrial Relations on Licensee Perspective on Probablistic Risk Analysis ML20155C2231998-10-29029 October 1998 Forwards Draft Ltr from STP Nuclear Operating Co on Action Needed for Implementation of Graded QA for Plant Units 1 & 2 for Placement in PDR ML20155C2651998-10-29029 October 1998 Forwards SG Insp Results Conducted in Oct 1998,to Be Placed in Pdr.Licensee Provided Info to Facilitate 981015 Conference Call ML20155C2171998-10-26026 October 1998 Notification of 981109-10 Meeting with Util to Obtain Info from Licensee for NRC Proposed risk-informed Insp & Assessment Program.Agenda Encl ML20154L9261998-10-0909 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980602-04 ML20154L4101998-10-0909 October 1998 Forwards NRC Operator Licensing Exam Repts 50-498/98-301 & 50-499/98-301,including Completed Graded Tests Administered on 980602-04 ML20154A0331998-09-24024 September 1998 Informs That Based on Review of Licensee 10CFR50.59 Evaluation of Environ Qualification of Mechanical Components,Staff Found That Proposed Change to UFSAR to Eliminate Meq Program Would Not Alter Any Plant Sys ML20151Y7231998-09-12012 September 1998 Notification of Licensee Meeting with Util on 981013 in Arlington,Tx Re Licensee Presentation Concerning Graded Quality Assurance Program at Plant ML20239A0941998-09-0303 September 1998 Notification of 980915 Meeting W/Util in Rockville,Md to Discuss Problems W/Implementing Graded QA,10CFR50.59,impact on risk-informed Applications & Comments on NRC Proposed Rev to 10CFR50.59 ML20239A1171998-09-0202 September 1998 Notification of 980915 Meeting W/Stp Nuclear Operating Co in Rockville,Md Re Licensee Presentation of Uses of Probabilistic Safety Assessment ML20151T6061998-09-0101 September 1998 Notification of Significant Licensee Meeting W/Util on 980918 to Discuss Licensee Insp Plans for Units 1 & 2 Replacement Steam Generators ML20236X8171998-08-0303 August 1998 Notification of Licensee Meeting W/Util on 980820 in Arlington,Tx to Discuss Certain Issues Ongoing at STP Site ML20249A6781998-06-16016 June 1998 Forwards Confirmatory Order Modifying Licenses NPF-76 & NPF-80 (Effective Immediately),For Transmittal to Ofc of Fr for Publication.W/O Encl ML20216J4491998-04-16016 April 1998 Notification of 980506 Meeting W/Util in Rockville,Md to Discuss Proposed Merger Between Aep & Central Southwest ML20217K9381998-04-0303 April 1998 Notification of 980413 Meeting W/Util in Rockville,Md to Discuss Licensee Desire for Update on Schedule for NRC Review of Licensee Application for Conversion to Improved Std TSs ML20197B0551998-03-0505 March 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam submittal,2nd & 3rd Exam Submittal as Given Operating Exam Administered on 971020-1205 1999-09-21
[Table view] |
Text
r o D April 26,1999 MEMORANDUM TO: File FROM: Thomas W. Alexion, Project Manager, Section 1 ORIG. SIGNED BY Project Directorate IV & Decommissioning Division of Licensing Project Management
SUBJECT:
DISCUSSIONS WITH LICENSEE ON ITS RESPONSE TO GENERIC LETTER 95-07," PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES, SOUTH TEXAS PROJECT, UNITS 1 AND 2 (TAC NOS. M93521 AND M93522)
The NRC staff needs to conduct a phone call with the licensee on the above subject. In order to conduct the phone call, the staff needs to provide the licensee with the attached discussion areas to make the call as productive as possible. Following the call, the staff may follow-up some or all of these discussion areas with a formal request for additional information.
The purpose of this memorandum is to place the attachment in the Public Document Room.
Docket Nos. 50-498 and 50-499
Attachment:
As stated DISTRIBUTION: ~
CDocket File (50-498 and 50-499)
PUBLIC lf memcumwV U
$b\
rE,0014 l DOCUMENT NAME: 1:\SOTEXAS\MEM93521.WPD *via 04/16/99 e-mail To receive a cofw of thes document enticafe in the box C8Copywfo attachment / enclosure E= Copy with attachrnent! enclosure N e No copy OFFICE PDIV-1/PM E PDIV-D/LA .6 EMEB/SC $ PDIV-1/SC 6 NAME TAlexion CJamerson h DTerao* RGramrh DATE / /99 h /8I/99h 04/16/99 4 /D/99 OFFICIAL RECORD COPY 9904290190 990426 PDR ADOCK 05000499 P PDR
p arru g g% UNITE 3 STATES g NUCLEAR REGULATORY COMMISSION 2
} WASHINGTON, D.C. 20eeH001
~s*****/ April 26,1999 MEMORANDUM T File FROM. 1 , Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management
SUBJECT:
DISCUSSIONS WITH LICENSEE ON ITS RESPONSE TO GENERIC LETTER 95-07, " PRESSURE LOCKING AND THERMAL BINDING OF SAFETY RELATED POWER-OPERATED GATE VALVES, SOUTH TEXAS PROJECT, UNITS 1 AND 2 (TAC NOS. M93521 AND M93522)
The NRC staff needs to conduct a phone call with the licensee on the above subject. In order to conduct the phone call, the staff needs to provide the licensee with the attached discussion areas to make the call as productive as possible. Following the call, the staff may follow-up some or all of these discussion areas with a formal request for additional information.
The purpose of this memorandum is to place the attachment in the Public Document Room.
Docket Nos. 50-498 and 50-499
Attachment:
As stated
. Discussion Areas for Phone Call Generic Letter 95-07. " Pressure Lockina and Thermal Bindina of Safetv-Related Power-Operated Gate Valves
- South Texas Proiect. Units 1 and 2
- 1. Your February 13,1996, submittal states that the high head hot leg isolation valves, 1/2-Sl0008A/B/C, and the low head safety injection hot leg isolation valves, 1/2-Sl0019A/B/C are susceptible to thermal-induced pressure-locking, are opened 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> into the accident, that a 23 psi /*F pressurization rate was applicable, that the Commonwealth (Comed) pressure locking methodology was used to calculate the thrust required for the valves to operate during pressure locking conditions, and that full voltage would be available to the valves actuators following the design-basis accident.
Describe the minimum normal environmental temperature that the valves can experience (the submittal states that maximum environmental temperature is approximately 150*F) and the basis for the 23 psi /*F pressurization rate. Testing conducted by Idaho National Engineering and Environmental Laboratories (INEEL) identified pressurization rates of 50 psi /*F. NUREG/CR-6611,"Results of Pressure Locking and Thermal Binding Test of Gate Valves," dacuments the results of this testing.
Describe your design-/ licensing-basis requiremerts for determining when full / degraded voltages are available.
Your submittal states that the Comed pressure-locking calculation assumed initial bonnet pressure to be equal to that of the static of head of water in the piping. Explain why the bonnets would not be initially pressurized to reactor coolant system normal operating pressure.
Explain if the temperature of these valves could increase during the cold leg recirculation phase of an accident or during plant heatup while the RHR system is operating.
- 2. In Attachment 1 to GL 95-07, the NRC staff requested that licensees include consideration of the potential for gate valves to undergo pressure locking or thermal binding during surveillance testing. During workshops on GL 95-07 in each region, the NRC staff stated that, if closing a safety-related power-operated gate valve for test or surveillance defeats the capability of the safety system or train, the licensee should perform one of the following within the scope of GL 95-07:
- a. verify that the valve is not susceptible to pressure locking or thermal binding while closed,
- b. follow plant technical specifications for the train / system while the valve is closed,
- c. demonstrate that the actuator has sufficient capacity to overcome these phenomena, or
- d. make appropriate hardware and/or procedural modifications to prevent pressure locking and thermal binding.
1 The staff stated that normally open, safety-related power-operated gate valves, which are closed for surveillance but must retum to the open position, would be evaluated within the scope of GL 95-07. Please discuss if valves that meet this criterion were included in your review.
- 3. Your February 13,1996, submittal states that the low head safety injection cold leg isolation valves,1/2-RH0031 A/B/C, are susceptible to pressure locking and the Comed pressure-locking methodology was used to demonstrate that the valves would operate during pressure-locking conditions. It appears that you are inappropriately using the Comed pressure-locking methodology to demonstrate that these valves will operate during a differential pressure condition in lieu of a pressure-locking condition. Verify that this is the correct understanding of your submittal.
- 4. You used an analytical method to demonstrate that valves would operate during thermal binding conditions. Discuss any testing that was performed to validate your methodology. It is difficult to accept methodologies as corrective action for GL 95-07 that have not been tested. j
- 5. Your February 13,1996, submittal states that your thermal binding methodology wm used te demonstrate that reactor coolant system normal and attemate charging flow isolation valves,1/2-CV0003 and 1/2-CV0006, would open during thermal binding conditions. Do you have any operating experience that demonstrates that the valves will operate during thermal binding conditions?
- 6. Comed recommends that, when using its methodology, minimum margins should be applied between calculated pressure-locking thrust and actuator capability. These j margins along with diagnostic equipment accuracy and methodology limitations are :
defined in a letter from Comed to the NRC dated May 29,1998 (Accession Number 9806040184). Explain if you are meeting these requirements for all valves for which the Comed pressure-locking methodology is used.
- 7. Explain why containment spray pump discharge valves,1/2-MOV-0001 A/B/C, are not susceptible to pressure locking following operation of the containment spray pumps with the discharge valves shut. Are there any pressure-locking scenarios where the valves will operate at locked rotor conditions until the containment spray pump develops full discharge pressure?
i
W April 26, 1999 b
MEMORANDUM TO: File FROM: Thomas W. Alexion, Project Manager, Section 1 ORIG. SIGNED BY Project Directorate IV & Decommissioning Division of Licensing Project Management
SUBJECT:
DISCUSSIONS WITH LICENSEE ON ITS RESPONSE TO GENERIC LETTER 95-07, " PRESSURE LOCKING AND THERMAL BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES, SOUTH TEXAS PROJECT, UNITS 1 AND 2 (TAC NOS. M93521 AND M93522)
The NRC staff needs to conduct a phone call with the licensee on the above subject. In order to conduct the phone call, the staff needs to provide the licensee with the attached discussion areas to make the call as productive as possible. Following the call, the staff may follow-up some or all of these discussion areas with a formal request for additional information.
The purpose of this memorandum is to place the attachment in the Public Document Room.
Docket Nos. 50-498 and 50-499
Attachment:
As stated DISTRIBUTION:
Docket File (50-498 and 50-499)
PUBLIC l
DOCUMENT NAME: 1:\SOTEXASWlEM93521.WPD *via 04/16/99 e-mail To recome e top ' Of this document indeste m the bow CaCopy wAo attachment / enclosure E= Copy with attachment / enclosure N e No copy OFFICE PDIV.1/PM S PDIV-D/LA 6 EMEB/SC C PDIV-1/SC 6 NAME TAlexion CJamerson bl/DTerso* RGramnh DATE A / /99 h /8I/99h 04/16/99 Q /D/99 )
OFFICIAL RECORD COPY )
i
t
- og p 1 UNITED STATES s* NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. seseHIM
- April 26, 1999 MEMORANDUM T . File l
l FROM: f Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV & Decommissioning
' l Division of Licensing Project Management l i
SUBJECT:
DISCUSSIONS WITH LICENSEE ON ITS RESPONSE TO GENERIC LETTER 95-07," PRESSURE LOCKING AND THERMAL BINDING OF
. SAFETY-RELATED POWER-OPERATED GATE VALVES, SOUTH l TEXAS PROJECT, UNITS 1 AND 2 (TAC NOS. M93521 AND M93522) l .
The NRC staff needs to conduct a phone call with the licensee on the above subject. In order to conduct the phone call, the staff needs to provide the licensee with the attached discussion areas to make the call as productive as possible. Following the call, the staff may follow-up some or all of these discussion areas with a formal request for additional information.
The purpose of this memorandum is to place the attachment in the Public Document Room.
1 l
Docket Nos. 50-498 and 50-499 l
Attachment As stated 1
1 l
l
4
,. Discussion Areas for Phone Qg[
Generic Letter 95-07. Pressure Lockina and Thermal Bindina of Safety-Related Power-Operated Gate Valves" South Texas Project. Units 1 and 2 l
- 1. Your February 13,1996, submittal states that the high head hot leg isolation valves, 1/2-Sl0008A/B/C, and the low head safety injection hot leg isolation valves, 1/2-S10019A/B/C are susceptible to thermal-induced pressure-locking, are opened 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> into the accident, that a 23 psi /*F pressurization rate was applicable, that the Commonwealth (Comed) pressure locking methodology was used to calculate the thrust required for the valves to operate during pressure locking conditions, and that full volteae would be available to the valves actuators following the design-basis accident.
Describe the minimum normal environmental temperature that the valves can experience (the submittal states that maximum environmental temperature is approximately 150*F) and the basis for the 23 psi /*F pressurization rate. Testing conducted by Idaho National Engineering and Environmental Laboratories (INEEL) identified pressurization rates of 50 psi /*F. NUREG/CR-6611, *Results of Pressure Locking and Thermal Binding Test of Gate Valves," documents the results of this testing.
Describe your design-/ licensing-basis requirements for determining when full / degraded voltages are available.
Your submittal states that the Comed pressure-locking calculation assumed initial bonnet pressure to be equal to that of the static of head of water in the piping. Explain why the bonnets would not be initially pressurized to reactor coolant system normal operating pressure.
Explain if the temperature of these valves could increase during the cold leg recirculation phase of an accident or during plant heatup while the RHR system is operating.
- 2. In Attachment 1 to GL 95-07, the NRC staff requested that licensees include consideration of the potential for gate valves to undergo pressure locking or thermal binding during surveillance testing. During workshops on GL 95-07 in each region, the NRC staff stated that, if closing a safety-related power-operated gate valve for test or surveillance defeats the capability of the safety system or train, the licensee should perform one of the following within the scope of GL 95 07:
- a. vertfy that the valve is not susceptible to pressure locking or thermal binding while closed,
- b. follow plant technical specifications for the train / system while the valve is closed,
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- c. demonstrate that the actuator has sufficient capacity to overcome these phenomena, or
- d. make appropriate hardware and/or procedural modifications to prevent pressure locking and thermal binding.
The staff stated that normally open, safety-related power-operated gate valves, which are closed for surveillance but must retum to the open position, would be evaluated within the scope of GL 95-07. Please discuss if valves that meet this criterion were -
included in your review.
- 3. Your February 13,1996, submittal states that the low head safety injection cold leg isolation valves,1/2-RH0031A/B/C, are susceptible to pressure locking and the Comed pressure locking methodology was used to demonstrate that the valves would operate during pressure-locking conditions. It appears that you are inappropriately using the Comed pressure-locking methodology to demonstrate that these valves will operate dJring a differential pressure Condition in lieu of a pressure-locking Condition. Verify that this is the correct understanding of your submittal.
- 4. You used an analytical method to demonstrate that valves would operate during thermal binding conoMns. Discuss any testing that was performed to validate your methodology. It is difficult to accept methodologies as corrective action for GL 95-07 that have not been tested.
- 5. Your February 13,1996, submittal states that your thermal binding methodology was used to demonstrate that reactor. coolant system normal and altamate charging flow isolation valves,1/2-CV0003 and 1/2-CV0006, would open during thermal binding conditions. Do you have any operating experience that demonstrates that the valves will operate during thermal binding conditions?
- 6. Comed recommends that, when using its methodology, minimum matgins should be applied between calculated pressure-locking thrust and actuator capability. These margins along with diagnostic equipment accuracy and methodology limitations are defined in a letter from Comed to the NRC dated May 29,1998 (Accession Number 9806040184). Explain if ycu are meating these requirements for all valves for which the Comed pressure-locking methodology is used.
- 7. Explain why containment spray pump discharge valves,1/2-MOV-0001A/B/C, are not susceptible to pressure locking following operation of the containment spray pumps with the discharge valves shut. Are there any pressure-locking scenarios where the valves will operate at locked rotor conditions until the containment spray pump develops full discharge pressure?
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