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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20205N9871999-04-14014 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990308-11 ML20203G0081999-02-12012 February 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 981102-06 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20149D7851997-07-14014 July 1997 Notification of Significant Licensee Meeting W/Util on 970731 in Arlington,Tx to Discuss Case Studies (Response Time & Reactor Feedwater Pump Trip Test) & Common Themes ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20134P5931997-02-21021 February 1997 Forwards Order Imposing Civil Monetary Penalty for Transmittal to Ofc of Fr for Publication.W/O Encl ML20132F5421996-12-19019 December 1996 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961007-11 ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20203B9891995-11-20020 November 1995 Discusses OI Rept 4-95-032 Re Alleged False Statements by Fire Watches to NRC Inspectors.Oe Will Consider Matter Closed from Enforcement Perspective Unless Different View Received within 3 Wks of Date of This Memo ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20236L5631994-08-10010 August 1994 Responds to Former Region V 930422 Request for NRR Evaluation of WPPSS Practices Associated W/Testing RHR Sys While Aligned in SPC Mode ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20247G1561989-05-15015 May 1989 Forwards Director'S Decision 89-03 in Response to 2.206 Petition Re BWR Stability.Petition Filed by Hiatt on Behalf of Ocre Expressing Concerns Re 890309 Power Oscillattion Event & Requested Action W/Respect to All BWRs ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195G7981987-07-31031 July 1987 Partially Deleted Memo Forwarding SALP Rept & Recommendations Re NRC Actions for Plant.W/O Encl IR 05000397/19870061987-07-0101 July 1987 Forwards Draft SALP Rept 50-397/87-06 for Feb-May 1987 for Review.Comments Requested at SALP Board Meeting Schedule for 870707 in Region V.Update of Tables 1-4 Included in Draft. W/O Rept ML20236B1451987-06-18018 June 1987 Forwards Response to DF Kirsch 870507 Memo Requesting Performance Analysis Info for Input to Facility SALP Rept. Review Results Provided in Encl.Encl Withheld ML20214M1381987-05-26026 May 1987 Provides Enforcement Guidance to Regions for Issues Re Control Room Habitability/Control Room Emergency Ventilation Sys Deficiencies.Summary of Plants Reviewed & Documents Describing Findings Encl ML20195G7931987-05-12012 May 1987 Forwards Insp & LER Data Tables for Use in Preparing Performance Analyses for Salp,Per DF Kirsch 870507 Memo. Tables Subj to Review & Comment Until SALP Process Complete. W/O Encls ML20214A0311987-05-12012 May 1987 Notifies of 870514 Briefing on Licensing & Operational Status of Plants Assigned to Project Directorate V,Including Diablo Canyon,Palo Verde,Rancho Seco,San Onfore,Trojan & WPPSS 2 ML20212M8601987-03-0909 March 1987 Forwards SER Re Concerns Identified in Plant Fire Protection Program,As Described in FSAR Through Amend 33.Concerns Resolved Except for Listed Items,Including Adequacy of Safe Shutdown Procedures.Review Excluded Amend 37 Items ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20215G1361986-10-14014 October 1986 Summary of 861006 Operating Reactor Events Meeting 86-35 Re Events Since Last Meeting on 860929.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Attendance List & Viewgraphs Encl ML20215F2751986-10-0606 October 1986 Forwards Action Timetable Re Coordinated Approach to Resolution of Fire Protection Issues at Facility ML20209A8611986-09-0202 September 1986 Forwards Matls Needed to Complete Assignment During Emergency Preparedness Exercise on 860916-19.W/o Encl IR 05000397/19860121986-08-25025 August 1986 Notification of 860828 Meeting W/Util in Walnut Creek,Ca to Discuss Apparent Violations Involving Equipment Qualification (50-397/86-12),Region V Team Insp 50-397/86-11 & Control of Combustible Matls ML20204G4051986-08-0404 August 1986 Notification of 860909 Meeting W/Utils in Bethesda,Md to Discuss Nrc/Util Living Schedules,Util Performance,Legal Considerations,Tech Spec Improvements & Severe Accident Policy/Degraded Core Programs.Proposed Agenda Encl ML20207J2451986-07-16016 July 1986 Forwards Request for Addl Info Re Util Application to Amend Tech Spec 4.6.4.1 Concerning Drywell Vacuum Breakers,For Transmittal to Licensee.Receipt of Info After 860731 Will Require Rev to 860831 Anticipated Review Completion Date ML20058K6041986-07-0303 July 1986 Informs of Telcon on Status of EA-86-110 Re Health Physics/ Emergency Planning & EA-86-070 Re Fire Protection ML20203B0881986-07-0202 July 1986 Forwards SALP Rept for Feb 1985 - Jan 1986,for Review.Salp Board Rated Licensee Performance Category 1 in Area of Outages & Category 2 in All Other Areas Except Fire Protection.W/O Encls ML20236Y1311986-04-25025 April 1986 Forwards List of Primary Containment Isolation Valves & Valve P&ID Locations as Referenced in Util 860117 & 0218 Request for Amend to License NPF-21 ML20198D7151986-04-24024 April 1986 Forwards Insp Rept 50-397/86-05,notice of Violation & Enforcement History,For Consideration & Action.Civil Penalty Unwarranted Since Fire Watches Immediately Posted & Safety Significance of Fire Loadings Limited ML17278A7091986-04-16016 April 1986 Advises That Deletion of Technical Memo 1227 Overlooked During Issuance of Amend 31 to Fsar.Memo Deleted as Result of Incorporation of Scn 83-135 Into Amend ML20195G7731986-03-14014 March 1986 Forwards Draft SALP Rept for Feb 1985 - Jan 1986,for Review & Comment at 860319 Meeting at Region V.Updated Tables 1 & 4 Also Encl.W/O Encl ML20154K1511986-03-0303 March 1986 Notifies That SALP Board 860312 Meeting Rescheduled for 860319 at Region V.Deviation from Instruction 0701 to Permit a Toth Attendance at B&W Training Course on 860303-15 in Best Interest of SALP Process ML20199D1311986-02-19019 February 1986 Informs That Proposed Recirculation Pump Vibration Testing Plan Acceptable,Based on Licensee Testing Procedure & Supporting Stress Analysis ML20203B1101986-02-13013 February 1986 Forwards Assessment of Lers,Including Results for Input Into SALP Rept for Feb 1985 - Jan 1986.LERs of Above Average Quality ML20195G7801986-02-0909 February 1986 Forwards Data Tables for Use in Preparing Performance Analysis for Salp.Insp Results & LERs Occurring During Last Month of SALP May Not Be Included in Tables.Tables Subject to Review & Comment Until SALP Process Completed.W/O Encl ML20215N3041986-01-30030 January 1986 Provides Summary of Review of Past Experience as Related to Handling of Nonradiological Issues.State of Wa Notified by NRC of Industrial Safety Concerns at Facility.Dm Kunihiro 851213 Memo to State of Wa Encl ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20149M8611986-01-24024 January 1986 Discusses 851202-06 Observation of Seven INPO Members & Two Industry Peer Evaluators During Conduct of Site Visit to Evaluate Three Training Programs at Plant.Significant Milestones Toward Accreditation of Training Programs Listed ML20198H2291986-01-22022 January 1986 Requests Date & Subj of Application for OL Issued on 840413.Info Needed to Complete Review of 850318 Transmittal of License Fee Data & Assessment of Fees & Contractual Costs Through 841222 ML20198G8771986-01-16016 January 1986 Forwards Brief Description & Evaluation of Util 850911 Proposed Tech Spec Change to Revise Composition of Corporate Nuclear Safety Review Board.Proposed Change Acceptable ML20198G8291986-01-0606 January 1986 Forwards Draft Response to 850718 Memo Re Inspector Feedback /Request for Technical Assistance on NUREG-0737,Item II.F.1.Response Based on Review of Util Position on Iodine plate-out ML20141E9281985-12-26026 December 1985 Recommends Survey of Plants Re Licensee Review of Preservice Insp Rept & Submittal of Relief Requests.Relief Requests from Preservice Insp Should Be Submitted Before Issuance of OL & Plant Startup to Permit NRC Review 1999-04-14
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20205N9871999-04-14014 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990308-11 ML20203G0081999-02-12012 February 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 981102-06 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20149D7851997-07-14014 July 1997 Notification of Significant Licensee Meeting W/Util on 970731 in Arlington,Tx to Discuss Case Studies (Response Time & Reactor Feedwater Pump Trip Test) & Common Themes ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20134P5931997-02-21021 February 1997 Forwards Order Imposing Civil Monetary Penalty for Transmittal to Ofc of Fr for Publication.W/O Encl ML20132F5421996-12-19019 December 1996 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961007-11 ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20203B9891995-11-20020 November 1995 Discusses OI Rept 4-95-032 Re Alleged False Statements by Fire Watches to NRC Inspectors.Oe Will Consider Matter Closed from Enforcement Perspective Unless Different View Received within 3 Wks of Date of This Memo ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20236L5631994-08-10010 August 1994 Responds to Former Region V 930422 Request for NRR Evaluation of WPPSS Practices Associated W/Testing RHR Sys While Aligned in SPC Mode ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20247G1561989-05-15015 May 1989 Forwards Director'S Decision 89-03 in Response to 2.206 Petition Re BWR Stability.Petition Filed by Hiatt on Behalf of Ocre Expressing Concerns Re 890309 Power Oscillattion Event & Requested Action W/Respect to All BWRs ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195G7981987-07-31031 July 1987 Partially Deleted Memo Forwarding SALP Rept & Recommendations Re NRC Actions for Plant.W/O Encl IR 05000397/19870061987-07-0101 July 1987 Forwards Draft SALP Rept 50-397/87-06 for Feb-May 1987 for Review.Comments Requested at SALP Board Meeting Schedule for 870707 in Region V.Update of Tables 1-4 Included in Draft. W/O Rept ML20236B1451987-06-18018 June 1987 Forwards Response to DF Kirsch 870507 Memo Requesting Performance Analysis Info for Input to Facility SALP Rept. Review Results Provided in Encl.Encl Withheld ML20214M1381987-05-26026 May 1987 Provides Enforcement Guidance to Regions for Issues Re Control Room Habitability/Control Room Emergency Ventilation Sys Deficiencies.Summary of Plants Reviewed & Documents Describing Findings Encl ML20195G7931987-05-12012 May 1987 Forwards Insp & LER Data Tables for Use in Preparing Performance Analyses for Salp,Per DF Kirsch 870507 Memo. Tables Subj to Review & Comment Until SALP Process Complete. W/O Encls ML20214A0311987-05-12012 May 1987 Notifies of 870514 Briefing on Licensing & Operational Status of Plants Assigned to Project Directorate V,Including Diablo Canyon,Palo Verde,Rancho Seco,San Onfore,Trojan & WPPSS 2 ML20212M8601987-03-0909 March 1987 Forwards SER Re Concerns Identified in Plant Fire Protection Program,As Described in FSAR Through Amend 33.Concerns Resolved Except for Listed Items,Including Adequacy of Safe Shutdown Procedures.Review Excluded Amend 37 Items ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20215G1361986-10-14014 October 1986 Summary of 861006 Operating Reactor Events Meeting 86-35 Re Events Since Last Meeting on 860929.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Attendance List & Viewgraphs Encl ML20215F2751986-10-0606 October 1986 Forwards Action Timetable Re Coordinated Approach to Resolution of Fire Protection Issues at Facility ML20209A8611986-09-0202 September 1986 Forwards Matls Needed to Complete Assignment During Emergency Preparedness Exercise on 860916-19.W/o Encl IR 05000397/19860121986-08-25025 August 1986 Notification of 860828 Meeting W/Util in Walnut Creek,Ca to Discuss Apparent Violations Involving Equipment Qualification (50-397/86-12),Region V Team Insp 50-397/86-11 & Control of Combustible Matls ML20204G4051986-08-0404 August 1986 Notification of 860909 Meeting W/Utils in Bethesda,Md to Discuss Nrc/Util Living Schedules,Util Performance,Legal Considerations,Tech Spec Improvements & Severe Accident Policy/Degraded Core Programs.Proposed Agenda Encl ML20207J2451986-07-16016 July 1986 Forwards Request for Addl Info Re Util Application to Amend Tech Spec 4.6.4.1 Concerning Drywell Vacuum Breakers,For Transmittal to Licensee.Receipt of Info After 860731 Will Require Rev to 860831 Anticipated Review Completion Date ML20058K6041986-07-0303 July 1986 Informs of Telcon on Status of EA-86-110 Re Health Physics/ Emergency Planning & EA-86-070 Re Fire Protection ML20203B0881986-07-0202 July 1986 Forwards SALP Rept for Feb 1985 - Jan 1986,for Review.Salp Board Rated Licensee Performance Category 1 in Area of Outages & Category 2 in All Other Areas Except Fire Protection.W/O Encls ML20236Y1311986-04-25025 April 1986 Forwards List of Primary Containment Isolation Valves & Valve P&ID Locations as Referenced in Util 860117 & 0218 Request for Amend to License NPF-21 ML20198D7151986-04-24024 April 1986 Forwards Insp Rept 50-397/86-05,notice of Violation & Enforcement History,For Consideration & Action.Civil Penalty Unwarranted Since Fire Watches Immediately Posted & Safety Significance of Fire Loadings Limited ML17278A7091986-04-16016 April 1986 Advises That Deletion of Technical Memo 1227 Overlooked During Issuance of Amend 31 to Fsar.Memo Deleted as Result of Incorporation of Scn 83-135 Into Amend ML20195G7731986-03-14014 March 1986 Forwards Draft SALP Rept for Feb 1985 - Jan 1986,for Review & Comment at 860319 Meeting at Region V.Updated Tables 1 & 4 Also Encl.W/O Encl ML20154K1511986-03-0303 March 1986 Notifies That SALP Board 860312 Meeting Rescheduled for 860319 at Region V.Deviation from Instruction 0701 to Permit a Toth Attendance at B&W Training Course on 860303-15 in Best Interest of SALP Process ML20199D1311986-02-19019 February 1986 Informs That Proposed Recirculation Pump Vibration Testing Plan Acceptable,Based on Licensee Testing Procedure & Supporting Stress Analysis ML20203B1101986-02-13013 February 1986 Forwards Assessment of Lers,Including Results for Input Into SALP Rept for Feb 1985 - Jan 1986.LERs of Above Average Quality ML20195G7801986-02-0909 February 1986 Forwards Data Tables for Use in Preparing Performance Analysis for Salp.Insp Results & LERs Occurring During Last Month of SALP May Not Be Included in Tables.Tables Subject to Review & Comment Until SALP Process Completed.W/O Encl ML20215N3041986-01-30030 January 1986 Provides Summary of Review of Past Experience as Related to Handling of Nonradiological Issues.State of Wa Notified by NRC of Industrial Safety Concerns at Facility.Dm Kunihiro 851213 Memo to State of Wa Encl ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20149M8611986-01-24024 January 1986 Discusses 851202-06 Observation of Seven INPO Members & Two Industry Peer Evaluators During Conduct of Site Visit to Evaluate Three Training Programs at Plant.Significant Milestones Toward Accreditation of Training Programs Listed ML20198H2291986-01-22022 January 1986 Requests Date & Subj of Application for OL Issued on 840413.Info Needed to Complete Review of 850318 Transmittal of License Fee Data & Assessment of Fees & Contractual Costs Through 841222 ML20198G8771986-01-16016 January 1986 Forwards Brief Description & Evaluation of Util 850911 Proposed Tech Spec Change to Revise Composition of Corporate Nuclear Safety Review Board.Proposed Change Acceptable ML20198G8291986-01-0606 January 1986 Forwards Draft Response to 850718 Memo Re Inspector Feedback /Request for Technical Assistance on NUREG-0737,Item II.F.1.Response Based on Review of Util Position on Iodine plate-out ML20141E9281985-12-26026 December 1985 Recommends Survey of Plants Re Licensee Review of Preservice Insp Rept & Submittal of Relief Requests.Relief Requests from Preservice Insp Should Be Submitted Before Issuance of OL & Plant Startup to Permit NRC Review 1999-04-14
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e SEP 0 91992 Docket No. 50-397 MEMORANDUM FOR: Albert Schwencer, Chief Licensing Branch No. 2 Division of Licensing FROM: Zoltan R. Rosztoczy, Chief Equipment Qualification Branch Division of Engineering
SUBJECT:
WASHINGTON PUBLIC POWER SUPPLY SYSTEM (WPPS)
NUCLEAR PROJECT 2, PURGE AND VENT VALVE OPERABILITY (II.E.4.2)
On February 17, 1982 an informal copy of the Washington Nuclear Power Project 2 (WNP-2) qualification analysis for the containment purge and vent valves was given to M. Haughey of the Equipment Qualification Branch (EQB) for staff comments. During the month of February, 1982 staff comments on the qualification documents were verbally given to WPPS. Additional qualification work required, particularly in the area of dynamic. flow loads, was identified in those discussions. Since that time, no additional qualification reports have been submitted, either formally or informally, nor have any been indicated to the staff as forthcoming.
Attachment A contains specific comments to the informal submittal of February 17, 1982. The qualification package as received February 17, 1982 does not represent a complete and acceptable qualification package for these valves under the combined DBA-LOCA plus SSE loads.
Attachment B is a standard request form for information for purge and vent valve operability qualification. The applicant should formally submit qualification documents in accordance with Attachment A. In addition, the questions in Attachment 1 to Attachment B should also be responded to.
W41aul signea Ey Zoltan R. Rosztoczy, Chief Equipment Qualification Branch Division of Engineering cc: R. Vollmer R. Auluck D. Eisenhut T. Restivo (BNL) i S. Varga M. Haughey' (rr
( G. Bagchi W. Johnston s~W SDO9240075820909~N ADGCW 05000397 O'm cs_/
DE:EQB DE DE:EQB MHu ahey J ag 11 ZRRosztoczy 9/ 7 /82 9/ d 82/ 9/ /82 l
i
- Attachment A Comments to WNP-2 Purge and Vent Valve Qualification Documents
- 1. The torque sizing letter of January 9, 1976, B1F to Burns and Roe, indicated the dynamic flow forces of air during normal operation were negligible and the seating torque was considered the governing design load. Dynamic loads under LOCA pressures were 4
not considered. WPPS should determine if the dynamic flow loads during DBA-LOCA pressures are negligible as compared to the seating torques. The dynamic flow loads must be based on test (either model or actual size),
t
- 2. The applicant should show the operator has the ability to close the valve at all angles. Dynamic torque loads will vary with disc angle. The April 17, 1976 letter 81F to Burns and Roe ,
indicated operator torque capability also varies with disc angle.
- 3. If the dynamic torque under LOCA pressure for these valves is greater than the seating torque, a new analysis should be performed to show the effects of combined LOCA dynamic loads plus SSE seismic loads.
- 4. Stress allowables for the analysis are yield strength values.
No additional margin is applied. Stress allowables should reflect some margin. For example: the maximum shear allowable should be .6 Sm (Sm'as defined by ASME B&PV code,Section III) 4 for ASME Section III Components or .4 Sy (Sy = yield strength, i allowable as defined by AISC) for all other components. In addition, ultimate strength was used for non pressure boundary components. For valves required to operate conservative allowables should be used to allow for deviations in manu-facturing. Margins should be conservatively applied.
- 5. The valve appears to have natural frequencies at 17.3 Hz and t
23.9 Hz but the seismic analysis for the valve assembly assumed the valve to be rigid. In addition, seismic quali-fication for a component which has a function beyond simple pressure boundary should be qualified by test.
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Attachmenc B Operability Qualification of Purge and Vent Valves Demonstration of operability of the containment purge and vent valves
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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 Plan Requirements," II.E.4.2 for containment purge and vent valves which are not sealed closed during operational conditions 1, 2, 3 and 4.
- 1. For each purge and vent valve covered in the scope of this review, the following documentation demonstrating compliance with the
" Guidelines for Demonstration of Operability of Purge and Vent Valves" (Attachment 2) is to be submitted for staff review:
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 (asymmetric 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" (Attachment 1) which relate to his valve.
- 3. Analysis, if used, should be supported by tests which estab-blish torque coefficients of the valve at various angles. As torque coefficients 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 rep resentative of actual field -
O
installations. For example, non-symmetric 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 size / type which is determined to represent the worst case load. Worst case flow direction, for example, should be considered.
- 5. For two valves in series where the second valve is a butterfly valve, the effect of non-symmetric flow from the first valve should be considered if the valves are within 15 pipe diameters of each other.
- 6. If the applicant takes credit for closure time vs. the buildup of containment 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 (if valves close faster at all angles of opening under loaded conditions, no load closure time may be used as conservative) and periodic inspection under tech. spec. require-ments should be performed to assure closure rate does not increase with time or use.
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Attachment 1 -
a Specific Valve Type Questions The following questiens 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) i.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 operation. Discuss active electrical components in the accumulator system, and the basis used to determine their quali-fication 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 their qualification for the environmental condition experienced. Is this system seismically 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 reduce voltage operation result in any significant change in stroke timing? Describe the emergency mode power source used.
E. Where electric motor and air operator units are equipped with handwheels, does their design provide for automatic re-engagement 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 torque limiting settings?
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Attachment 2
- Guidelines for Demonstration .
Of Operability of Purge and Vent Valves .
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 which 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, in-situ 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 determination 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.
The following considerations apply when testing is chosen as a means for demonstrating valve operability:
Bench Testing A. Bench testing can be used to demonstrate suitability of the in-service valve by reason of its traceability in design to a test valve. The following factors should be considered when qualifying valves through bench testing.
- 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 downstream and valve orientation are simulated.
- 3. Whether the following load and environmental factors were conside r.ed
- a. Simulation of LOCA b.* Seismic loading
- c. Temperature soak
- d. Radiation exrosure
- e. Chemical exposure
- f. 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.
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In-Situ Testina
' 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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