Forwards Operability Qualification of Purge & Vent Valves & Guidelines for Demonstration of Operability of Purge & Vent Valves.Info Sought Should Be Provided as Soon as PossibleML20127C298 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Nine Mile Point, Perry, Harris, Hope Creek, Braidwood, Seabrook, River Bend, Vogtle, South Texas, 05000000, Marble Hill |
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Issue date: |
11/09/1984 |
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From: |
Noonan V Office of Nuclear Reactor Regulation |
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To: |
Knighton G, Schwencer A, Youngblood B Office of Nuclear Reactor Regulation |
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Shared Package |
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ML20126J910 |
List: |
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References |
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FOIA-84-926, TASK-2.E.4.2, TASK-TM NUDOCS 8411200132 |
Download: ML20127C298 (7) |
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Similar Documents at Beaver Valley, Millstone, Nine Mile Point, Perry, Harris, Hope Creek, Braidwood, Seabrook, River Bend, Vogtle, South Texas, 05000000, Marble Hill |
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20217N4611999-10-22022 October 1999 Forwards Revised Pages 11,14 & 71 of Rept & Order Dtd 990608.Revs Are Textual Changes to Clarify & Confirm Action Taken by Nuclear Decommissioning Financing Committee ML20217P5261999-10-20020 October 1999 Forwards Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217E9841999-10-14014 October 1999 Forwards Petition for Leave to Intervene Submitted on 991006 by Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone ML20217F3351999-10-14014 October 1999 Notification of 991103-04 Southern Nuclear Operating Licensing Workshop in Birmingham,Alabama with Goal of Improving Licensing Interface Between Licensee & NRC ML20217M4281999-10-0808 October 1999 Requests That Attached Request for Addl Info Be Placed in Pdr.Informs That RAI Faxed to J Bailey on 991008 & Will Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC Staff & SNC Staff ML20217E1501999-10-0707 October 1999 Notification of 991022 Meeting with NMPC to Discuss Nine Mile Point Performance as Documented in Mid-Cycle PPR of Nine Mile Point Nuclear Station ML20217D7031999-10-0707 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 ML20212K8811999-10-0404 October 1999 Notification of 991014 Meeting with Util in Rockville,Md to Discuss Improved Std TS Conversion Process for Plant,Units 1 & 2 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 ML20216F5061999-09-16016 September 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld ML20216F3591999-09-15015 September 1999 Informs That Encl SRM on COMSECY-99-016 Being Released to Public,Effective 990915.Encl Documents Including 990406 SRM in Response to Millstone Independent Review Team 990312 Rept & 990713 Memo from G Caputo Previously Released ML20212C0761999-09-15015 September 1999 Notification of 990930 Meeting with Firstenergy Nuclear Operating Co in Rockville,Md to Discuss Licensee Recent Submittal Requesting Five Percent Power Uprate ML20211K1431999-09-0202 September 1999 Notification of 990920 Meeting with Util in Rockville,Md to Discuss Recent Developments in New England Re Industry Deregulation & Restructuring Affecting Nu Use of Performance Indicators as Operating Plant ML20211K8611999-09-0101 September 1999 Informs That There Has Been Some Confusion Re Recently Issued ODCM Generic Section Rev Which Needs to Be Clarified. Clarifications Are Listed ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues 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 ML20211E1491999-08-23023 August 1999 Notification of Licensee Meeting with Util on 990830 to Discuss Recent Refueling Maint Outage 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 ML20210U1461999-08-13013 August 1999 Notification of 990827 Meeting with NNECO in King of Prussia,Pennsylvania to Discuss Engineering Initiatives & Backlog Management ML20210S6371999-08-13013 August 1999 Informs That Attached Info Transmitted by Facsimile on 990813 to P Duke of Pse&G to Facilitate Upcoming Conference Call in Order to Clarify Licensee Submittal ,which Provided Response to GL 98-04 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 ML20210L6431999-08-0606 August 1999 Notification of 990901 Meeting with NMP in Rockville,Md to Discuss NMP Plans to File Application Re Transfer of Interest & Authorities Under Plant Licenses to Amergen ML20210M6841999-08-0505 August 1999 Notification of Licensee Meeting with Util on 990914 in Arlington,Tx to Discuss New Mgt Team Introduction & Site Status ML20210P0141999-08-0505 August 1999 Forwards Licensee Response to Facility Design & Operation for NRC Staff Questions Re Individual Operator Exam Appeals ML20210P1361999-08-0404 August 1999 Notification of 990817 Meeting with Util in Rockville, Maryland to Discuss Status of Licensing Actions Submitted by Comm Ed & Plan for Proposed Licensing Workshop ML20210K4141999-08-0404 August 1999 Forwards Signed Originals of DD Issued Under 10CFR2.206. Without Encl ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20210E9311999-07-26026 July 1999 Notification of 990825 Public Meeting in Waterford,Ct Re PSDAR for Plant Unit 1 ML20210K1421999-07-22022 July 1999 Informs That Recipient Designated Chairman of Millstone Assessment Panel & E Adensam,Designated Co-Chairman.Panel Established to Assist Region I & NRR in Coordination of NRC Resources for Performance Monitoring & Inspecting Millstone ML20210C1631999-07-19019 July 1999 Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld ML20210C7061999-07-16016 July 1999 Forwards Facility Submitted Outline & Initial Exam Submittal for Operator Licensing Exams Administered During Wk of 990607 ML20209H2231999-07-16016 July 1999 Forwards Operator Licensing Exam Repts 50-456/99-301(OL) & 50-457/99-301(OL) of Exam Administered During Wk of 990607 ML20209G2421999-07-14014 July 1999 Notification of 990722 Meeting with License in Rockville, MD to Discuss Changes in EOI Licensing Organization Including Division of Responsibilities within New EOI Corporate Licensing Group ML20209G6721999-07-14014 July 1999 Forwards Draft Request for Addl Info Re Inservice Insp - Second 10 Yr Interval ML20209G0541999-07-13013 July 1999 Submits Director'S Guidance 99-001,effective Immediately,As Result of SRM in Response to Recommendations in Plant Independent Review Team Rept, ML20209F6111999-07-12012 July 1999 Revised Notification of 990805 Meeting with Util to Discuss Radiation Protection Issues Identified in NRC Insps Repts 50-458/98-10 & 50-458/99-04 ML20209G2611999-07-12012 July 1999 Forwards Draft Request for Addl Info Re GL 96-06 Response 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 ML20209D8271999-07-0707 July 1999 Notification of 990719 Licensee Meeting in Arlington,Tx to Discuss Failed Fuel Recovery Project 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 ML20212J5161999-07-0101 July 1999 Documents,For Public Record,Interaction Between NNECO & NRC Staff Re Licensee Proposed Licensing Action Now Being Reviewed by NRC Staff ML20209D7721999-06-29029 June 1999 Notification of 990715 Meeting 99-39 with Util in Waterford, CT Re Corrective Action & Safety Conscious Work Environ/ Employee Concerns Program Team Exit Meeting ML20209D7621999-06-29029 June 1999 Notification of Meeting 99-40 on 990715 with Nuclear Energy Advisory Council in Waterford,Ct to Discuss Millstone Safety Conscious Work Environ/Employee Concerns Program ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 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 ML20196G0321999-06-24024 June 1999 Notification of 990726 Meeting with Util to Discuss Radiation Protection Issues 1999-09-21
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20217N4611999-10-22022 October 1999 Forwards Revised Pages 11,14 & 71 of Rept & Order Dtd 990608.Revs Are Textual Changes to Clarify & Confirm Action Taken by Nuclear Decommissioning Financing Committee ML20217J8951999-10-21021 October 1999 Staff Requirements Memo Re Affirmation Session on 991021, Rockville,Md (Open to Public Attendance) ML20217P5261999-10-20020 October 1999 Forwards Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217F3351999-10-14014 October 1999 Notification of 991103-04 Southern Nuclear Operating Licensing Workshop in Birmingham,Alabama with Goal of Improving Licensing Interface Between Licensee & NRC ML20217E9841999-10-14014 October 1999 Forwards Petition for Leave to Intervene Submitted on 991006 by Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone ML20217D3601999-10-13013 October 1999 Staff Requirements Memo on SECY-99-223 Re Millstone Independent Review Team 990312 Rept on Allegations of Discrimination in NRC Ofc of Investigation Cases Nda: 1-96-002,1-96-007 & 1-97-007 & Associated Recommendation 6 ML20217M4281999-10-0808 October 1999 Requests That Attached Request for Addl Info Be Placed in Pdr.Informs That RAI Faxed to J Bailey on 991008 & Will Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC Staff & SNC Staff ML20217E1501999-10-0707 October 1999 Notification of 991022 Meeting with NMPC to Discuss Nine Mile Point Performance as Documented in Mid-Cycle PPR of Nine Mile Point Nuclear Station ML20217D7031999-10-0707 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 ML20212K8811999-10-0404 October 1999 Notification of 991014 Meeting with Util in Rockville,Md to Discuss Improved Std TS Conversion Process for Plant,Units 1 & 2 ML20212L3481999-10-0101 October 1999 Forwards Document Re Replacement SG Water Level Trip Setpoint Differences to Be Placed in PDR ML20212F5401999-09-24024 September 1999 Staff Requirements Memo Re 990924 Affirmation Session Concerning SECY-99-236, Firstenergy Nuclear Operating Co, Local 29 Petition to Waive Time Limits in 10CFR2.1305 & Suppl Comments 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 ML20216F5061999-09-16016 September 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld ML20212C0761999-09-15015 September 1999 Notification of 990930 Meeting with Firstenergy Nuclear Operating Co in Rockville,Md to Discuss Licensee Recent Submittal Requesting Five Percent Power Uprate ML20216F3591999-09-15015 September 1999 Informs That Encl SRM on COMSECY-99-016 Being Released to Public,Effective 990915.Encl Documents Including 990406 SRM in Response to Millstone Independent Review Team 990312 Rept & 990713 Memo from G Caputo Previously Released ML20211K1431999-09-0202 September 1999 Notification of 990920 Meeting with Util in Rockville,Md to Discuss Recent Developments in New England Re Industry Deregulation & Restructuring Affecting Nu Use of Performance Indicators as Operating Plant ML20211K8611999-09-0101 September 1999 Informs That There Has Been Some Confusion Re Recently Issued ODCM Generic Section Rev Which Needs to Be Clarified. Clarifications Are Listed ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues 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 ML20211E1491999-08-23023 August 1999 Notification of Licensee Meeting with Util on 990830 to Discuss Recent Refueling Maint Outage 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 ML20210S6371999-08-13013 August 1999 Informs That Attached Info Transmitted by Facsimile on 990813 to P Duke of Pse&G to Facilitate Upcoming Conference Call in Order to Clarify Licensee Submittal ,which Provided Response to GL 98-04 ML20210U1461999-08-13013 August 1999 Notification of 990827 Meeting with NNECO in King of Prussia,Pennsylvania to Discuss Engineering Initiatives & Backlog Management 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 ML20210L6431999-08-0606 August 1999 Notification of 990901 Meeting with NMP in Rockville,Md to Discuss NMP Plans to File Application Re Transfer of Interest & Authorities Under Plant Licenses to Amergen ML20210P0141999-08-0505 August 1999 Forwards Licensee Response to Facility Design & Operation for NRC Staff Questions Re Individual Operator Exam Appeals ML20210M6841999-08-0505 August 1999 Notification of Licensee Meeting with Util on 990914 in Arlington,Tx to Discuss New Mgt Team Introduction & Site Status ML20210P1361999-08-0404 August 1999 Notification of 990817 Meeting with Util in Rockville, Maryland to Discuss Status of Licensing Actions Submitted by Comm Ed & Plan for Proposed Licensing Workshop ML20210K4141999-08-0404 August 1999 Forwards Signed Originals of DD Issued Under 10CFR2.206. Without Encl ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20210E9311999-07-26026 July 1999 Notification of 990825 Public Meeting in Waterford,Ct Re PSDAR for Plant Unit 1 ML20210K1421999-07-22022 July 1999 Informs That Recipient Designated Chairman of Millstone Assessment Panel & E Adensam,Designated Co-Chairman.Panel Established to Assist Region I & NRR in Coordination of NRC Resources for Performance Monitoring & Inspecting Millstone ML20210C1631999-07-19019 July 1999 Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld ML20210C7061999-07-16016 July 1999 Forwards Facility Submitted Outline & Initial Exam Submittal for Operator Licensing Exams Administered During Wk of 990607 ML20209H2231999-07-16016 July 1999 Forwards Operator Licensing Exam Repts 50-456/99-301(OL) & 50-457/99-301(OL) of Exam Administered During Wk of 990607 ML20209G6721999-07-14014 July 1999 Forwards Draft Request for Addl Info Re Inservice Insp - Second 10 Yr Interval ML20209G2421999-07-14014 July 1999 Notification of 990722 Meeting with License in Rockville, MD to Discuss Changes in EOI Licensing Organization Including Division of Responsibilities within New EOI Corporate Licensing Group ML20209G0541999-07-13013 July 1999 Submits Director'S Guidance 99-001,effective Immediately,As Result of SRM in Response to Recommendations in Plant Independent Review Team Rept, ML20209G2611999-07-12012 July 1999 Forwards Draft Request for Addl Info Re GL 96-06 Response ML20209F6111999-07-12012 July 1999 Revised Notification of 990805 Meeting with Util to Discuss Radiation Protection Issues Identified in NRC Insps Repts 50-458/98-10 & 50-458/99-04 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 ML20209D8271999-07-0707 July 1999 Notification of 990719 Licensee Meeting in Arlington,Tx to Discuss Failed Fuel Recovery Project ML20216F3651999-07-0707 July 1999 Staff Requirements Memo Re COMSECY-99-016, Recommendations 2 & 3 of Mirt,Re Witness Credibility & OI Conclusions,Staff Requirements Memo ML20212J5161999-07-0101 July 1999 Documents,For Public Record,Interaction Between NNECO & NRC Staff Re Licensee Proposed Licensing Action Now Being Reviewed by NRC Staff ML20209D7721999-06-29029 June 1999 Notification of 990715 Meeting 99-39 with Util in Waterford, CT Re Corrective Action & Safety Conscious Work Environ/ Employee Concerns Program Team Exit Meeting 1999-09-24
[Table view] |
Text
. _ _ _ _ _ _ _ _ _ _ _ _ _ _
, o 8 UNITED STATES o
- NUCLEAR REGULATORY COMMISSION wash
- NGTON, D. C. 20655
/
NOV 9 1984 r \
Docket Nos: 50-412, 50-456, 50-354, 50-546, 50-423, l
50-410, 50-440, 50-458, 50-443, 50-400, 50-498, 50-424 i
MEMORANDUM FOR: B. Joe Youngblood, Chief Licensing Branch No.1 Albert Schwencer, Chief l Licensing Branch No. 2 l
George Knighton, Chief Licensing Branch No. 3 l
Elinor Adenson, Chief Licensing Branch No. 4 l
1 Division of Licensing l FROM: Vincent S. Noonan, Chief Equipment Qualification Branch Division of Engineering
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON l CONTAINMENT PURGE AND VENT VALVE OPERABILITY TMI II.E.4.2(6)
The attachments to this memo were part of the SQRT and PVORT request for additional information (attachments 4 and 5) previously made for the following plants:
Name of Plant Docket No.s Beaver Valley 2 50-412 Braidwood 1 50-456 Hope Creek 1 50-354 Marble Hill 1 50-546 i Millstone 3 50-423 Nine Mile Point 2 -
0 0
ve Bend 1 50-458 Seabrook 1 50-443 Shearon Ha is 1 South Te s Vogtle f 50-400 50-498 50-424
\\
b b /
h h
The information sought on the demonstration of containment purge and vent ~
valve operability should be provided as soon as possible. There is no need to wait until the SQRT and PVORT audits to submit the requested information.
Submittals on containment purge and vent valve operability made within one year prior to licensing generally result in a license condition. Please request the applicants to address TMI II.E.4.2(6) on an expedited basis.
J Vincent S. Noonan, Chief Equipment Qualification Branch Division of Engineering cc: See attached
Contact:
R. Wright x28209 cc: G. Bagchi B. Miller, BNL C. Miller, INEL D. Wagner A. Vietti M. Miller L. Lazo N. Katambi J. Stefano J. Stevens E. Weinkam M. Haughey V. Nurses E. Doolittle
Attachment #4 Operability Qualification of Purge and Vent. Valves i Demonstration of operability of the containment purge and vent valves and the ability of these valves to close during a design basis accident ,
is necessary to assure containment isolation. This demonstration of _
operability is required by NUREG-0737, " Clarification of TMI Action I
Plan Requirements," II.E.4.2 for containment purge and vent valves which are not sealed closed during operational conditions 1, 2, 3 ani 4.
i 1.
For each purge and vent valve covered in the scope of this review, the following documentation demonstra'ing compliance with the
" Guideline's for Demonstration of O Valves" (attached, Attachment #5) perability of Purge and Vent review: is to be submitted for staff A. Dynamic Torque Coefficient Test Reports (Butterfly valves only) - including a description of the test setup. -
B. Operability Demonstration or In-situ Test Reports (when used)
C. Stress Reports D. Seismic Reports for Valve Assembly (valve and operator) and associated parts.
E.
Sketch or description of each valve installation showing the following (Butterfly valves only):
- 1. direction of flow
- 2. disc closure direction
- 3. curved side of disc, upstream or downstream (asymetric discs)
- 4. orientation and distance of elbows, tees, bends, etc.
within 20 pipe diameters of valve
- 5. shaft orientation
- 6. distance between valves F.
Demonstration that the maximum combined torque developed by -
the valve is below the actuator rating.
- 2. The applicant should respond to the " Specific Valve Type Questions" (attached) which relate to his valve.
l
~_
- -- .,-e c , _ - -. r --.--y -
J .
2-3.
! Analysis, if used, should be supported by tests which establish torque '
coefficients of .the valve at various angles. As torque coefficients .
~
i' in butterfly valves are dependent on disc shape aspect ratio, angle of closure flow direction and approach flow, these things should be accurately represented during tests. Specifically, piping installations (upstream and downstream of the valve) during the test should be repre-
- sentative of actual field installations. For example, non-symetric approach flow from an elbow upstream of a valve can result in fluid dynamic torques of double the magnitude of those found for a valve with straight piping upstream and downstream.
- 4. In-situ tests, when performed on a representative valve, should be performed on a valve of each sinze/ type which is determined to ,
represent the worst case load. Worst case flow direction, for example, should be considered.
For two valves in series where the second valve is a butterfly valve, the effect of non-symetric flow from the first valve should be considered if the valves are within 15 pipe diameters of each other.
5.
If the applicant takes credit for closure time vs. the buildup of contain-ment pressure, he must demonstrate that the method is conservative with respect to the actual valve closure rate. Actual valve closure rate is to be determined under both loaded and unloaded conditions and periodic inspection under tech. spec. requirements should be performed to assure closure rate does not increase with time or use.
4 4
e 1
1 I
~ _ _ . , . _ ,_ _. _ . . - , _ . . _ ..__ _
l-1 Specific Valve Type ' Questions '
r The following questions apply to specific valve types only 'and need to be ~ ~
answered only where applicable. If not applicable, state so.
A'. Torque Due To Containment Backpressure Effect (TCB)
For those ' air operated valves located inside containment, is the operator design of a type that can be affected by the containment pressure rise (backpressure effect) 1.e. where the containment pressure acts to reduce the operator torque capability due to TCB. Discuss the operator design with respect to the air vent and bleeds. Show how TCB was calculated (if applicable). - -
B.
- Where air operated valve assemblies use accumulators as the fail-safe feature, describe the accumulator air system configuration and its oper-ation. Discuss and the basis us, active electrical . components in the accumulator system.
i ed to determine their qualification for the environmental conditions experienced. Is this system seismically designed? How is the allowable leakage from the accumulators determined and monitored.
C.
For valve assemblies requiring a seal pressurization system (inflatable '
main seal). describe the air pressurization system configuration and operation including means used to determine that valve closure and seal pressurization have taken place. Discuss active electrical components in this system, and the basis used to determine their qualification for the environmental condition experienced. Is this system seismfLeally designed?
D. Where electric motor operators are used to close the valve has the minimum available voltage to the electric operator under both
~
normal or emergency modes been determined and specified to the, operator manufacturer to assure the adequacy of the operator to stroke the valve at accident conditions with these lower limit voltages available? Does this reduced voltage operation result in any significant change in stroke timing? Describe the ~ emergency mode power source used.
I
- E. Where electric motor and air operator units are equipped with handwheels, does their design provide for automatic re-engagement i
of the motor operator following the handwheel mode of operation?-
If not.~what steps are taken to preclude the possibility of the
. valve being left in the handwheel mode following some maintenance, test etc. type operation?
- F. For electric motor operated valves have the torques developed during operation been found to be less than the t.orque limiting settings?
l .
- --,,,-e ---n---,, .--,,o-- -,,,--,--_m,,,,-w-- -
g -,--w,-,-,,w,,,,,wn$ ,,. - - , - ------_,,-n ,,-~~~-e-.4 , en--
j c':.
! . Attachment #5 i
GUIDELINES FOR DEMONSTRATION OF OPERABILITY OF PURGE AND i
i VENT VALVES i
OPERABILITY In order to establish operability it must be shown that the valve actuator's torque capability has sufficient margin to overcome or resist the torques and/or forces (i.e., fluid dynamic, bearing, seating, friction) that resist closure when stroking from the initial open position to full seated (bubble tight) in the time limit specified. This should be predicted on the pressure (s) established in the containment following a design basis LOCA. Considerations which should be addressed in assuring valve design adequacy include:
~
- 1. Valve closure rate versus time - i.e., constant rate or other.
- 2. Flow direction through valve; AP across valve.
- 3. Single valve closure (inside containment or outside containment valve) or simultaneous closure. Establish worst case.
- 4. Containment back pressure effect on closing torque margins of air operated valve vhich vent pilot air inside containment.
- 5. Adequacy of accumulator (when used) sizing and initial charge for valve closure requirements.
- 6. For valve operators using torque limiting devices - are the settings of the devices compatible with the torques required to operate the valve during the design basis condition.
- 7. The effect of the piping system (turns, branches) upstream and downstream
- of all valve installations.
- 8. The effect of butterfly valve disc and shaft orientation to the fluid '
mixture egressing from the containment.
DEMONSTRATION Demonstration of the various aspects of operability of purge and vent valves may be by analysis, bench testing, insitu testing or a combination of these means.
Purge and vent valve structural elements (valve / actuator assembly) must be evaluated to have sufficient stress margins to withstand loads imposed while valve closes during a design basis accident. Torsional shear, shear, bending, tension and compression loads / stresses should be considered. Seismic loading should be addressed. '
Once valve closure and structural integrity are assured by analysis, testing or a suitable combination, a deterinination of the sealing integrity after closure and long term exposure to the containment environment should be evaluated. Emphasis should be directed at the effect of radiation and of ~
the containment spray chemical solutions on seal material. Other aspects such as the effect on sealing from outside ambient temperatures and debris should be considered.
J
...! E..* ..
t I '
r
-2 t
The following considerations apply when testing is chosen as a means for demonstrating valve operability: i
! Bench Testing l '
A.
j Bench testing can be used to demonstrate suitability of the in-service valve by reason of its traceability in design to a test valve.
9
. factors should be considered when qualifying valves through bench testing.The follo I 1.
Whether a valve was qualified by testing of an identical valve assembly or by extrapolation of data from a similarly designed valve.
- 2. Whether measures were taken to assure that piping upstream and down-stream and valve orientation are simulated.
- 3. Whether the following load and environmental factors were considered i a. Simulation of LOCA i
- b. Seismic loading
- c. Temperature soak
- d. Radiation exposure
- e. Chemical exposure
- d. Debris B.
Bench testing of installed valves to demonstrate the suitability of the specific valve to perform its required function during the postulated design basis accident is acceptable.
1.
The factors listed in items A.2 and A.3 should be considered when taking this approach.
In-Situ Testing In-situ testing of purge and vent valves may be performed to confirm the
!' suitability of the valve under actual conditions. When performing such tests, the conditions (loading, environment) to which the valve (s) will be subjected during the test should simulate the design basis accident.
NOTE:
Post test valve examination should be performed to establish structural integrity of the key valve / actuator components.,
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