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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
[Table view] |
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MEMORANDUM FOR: R. Tedesco, Assistant Director for Licensino/DL .
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FROM: L. Rubenstein, Assistant Director for Core and Con,taTn '
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SUBJECT:
REVIEW SCHEDULE FOR WPPSS-2 The present NRR work schedule calls for a Safety Evaluation Report (SER) on the WPPSS-2 application by February 12, 1982. If we are to meet this SER date with-out an excessive number of open items in the area of dynamic loads in the sup-pression pool, we will need your assistani:e in getting the applicant to acceler-ate his work program in the associated loads definition area. Specifically, we will need the applicant's final submittal on load definition by August 12, 1981.
The background information dealing with this concern is as follows. In January 1981 we had a meeting with the applicant to discuss his improved chugging and condensation oscillation load methodologies. Formal documentation of this in-formation was scheduled for early May 1981. During the January meeting, we in-fonned the applicant that due to the availability of staff approved generic load specifications, they will have to justify the need for a plant unique re-view to the Director, Division of Systems Integration (DSI) (see memorandum from F. Eltawila to W. Butler dated Febesary 9,1981 (Enclosure 1). We also indicated that if such a plant unique review was found to be necessary, our review could not begin before January 1982, due to the severe shortage in staff resources.
Since then, the applicant has neither requested a meeting with the DSI Director to justify the need for a plant unique review nor submitted the docu$entation for the new plant unique methodologies.
The accelerated licensing schedoles in NRR has brought our reviews for LaSalle, Zininer, Shoreham and Susquehanna to substantial completion. As a result we are in a position to acconsnodate a limited amount of plant unique review for WPPSS-2.
Ilowever, based on prior experience on this subject of load definition and based on our understanding of the plant unique approaches being used by the WPPSS-2 applicant, we expect to need at least six months to complete our review once the associated documents are filed.
Accordingly, we request your assistance in assuring that the WPPSS-2 load deft-nition program proceeds on a schedule that is consistent with our licensing schedule. This means a complete description of the WPPSS-2 load definition methodologies (SRV load methodology, chugging load methodology and condensation oscillation load methodology) needs to be filed no later than August 12, 1982.
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MEMORANDUM FOR: W. Butler, Chief, Containment Systems Branch, DSI FROM: F. Eltawila, Containment Systems Branch, DSI
SUBJECT:
MEETING WITH WPPSS TO DISCUSS CONTAINMENT HYDRODYNAMIC LOADS FOR WNP-2 (JANUARY 2,1981, BETHESDA, MARYLAND)
In a letter dated December 19, 1980, the Washington Public Power Supply System (WPPSS) requested a meeting with the staff to discuss the chugging and conden-sation oscillation (CO) load definitions. Preliminary results from the ongoing plant unique chugging and C0 methodologies were presented to the staff during the meeting of January 21, 1981. An attendance list and a copy of the meeting handouts are enclosed.
Background
UPPSS initiated a program to develop an improved chugging load specification representing a reduction in the loads from the conservative lead plant chugging load specification set forth in NUREG-0487. A report titled, " Chugging Loads -
Improved Definitien and Application Methodology to Mark II Containments," was submitted to the staff in 1979 describing the WPPSS method. The staff reviewed this report and expressed concerns regarding the statistical averaging of the 4T data to arrive at a source specification at the vent exit.
During 1979 and early 1980, the Mark II Owners Group conducted additional tests on a modified 4T facility (4TC0) to better understand the LOCA related condensa-tion phenomena. Results of the 4TC0 tests led to the raodification of the NUREG-0487 specified lead plant CO and chugging pool boundary loads. The staff. is currently preparing Supplement 2 to NUREG-0487 containing an evaluation of the proposed alternatives to the lead plant CO and chugging load specifications.
The staff requested WPPSS to factor in the recently developed data from the 4TC0 l tests into the present improved chugging load definition, recognizing that its concerns regarding the statistical averaging of the 4T data, which is utilized by WPPSS, remain unanswered.
In addition to the plant unique chugging load definition, WPPSS advised the staff, in a letter dated October 1,1980, of preliminary indications that the generic CO l load definition may not be tolerable for WNP-2 and plant unique review may also be necessary. This item was not previously identified by the applicant as requir-ing a plant unique review.
WPPSS Presentation .
I. Improved Chugging load Methodology Dr. M. Ettouney of Burns & Roe provided an overview of the new improved chugging load methodology for application to WNP-2 containment. The load L a a c ni Q f.
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m t TE3 0 m7 W. Butler 2 valuation methodology reflects the data obtained from the 4T tests that was utilized in the original chugging load report and the new 4TCO test data.
Engineering evaluation of the 4TCO data base indicated that the chugging data can be grouped into two distinct types. Each excites different modes of the 4T system and, therefore, it 's not appropriate to consider them together in the statistical evaluation to arrive at source specifications.
The two groups are:
- 1) Normal chugs, similar'to those observed in the 4T data, influenced by vent response; and
- 2) Super chugs, with characteristics (pressure amplitude and frequency content) differer.t from those of the normal chugs, influenced by both the vent as well as the rest of the 4T system.
The improved load definition methodology for the normal chugs is the same as presented in the present chugging load report with the necessary amplf-tude changes. This report was previously reviewed by the staff and it was concluded that sounder arguments than those presented should be given to justify the statistical analyses of the 4T data to arrive at a conservative source specification.
It was also concluded that available multi-vent test data should be studied to verify the statistical averaging of the 4T data.
A new improved load definition methodology for the superchug (a total of 7 chugs have been identified as superchugs) has been developed. This new method accounts for the 4TCO facility components whose signature, such as wave form (acceleration vs pressure), water and steam properties, is pres-ent in the superchug boundary pressure traces. It was determined that the normal chug will be best represented by a pressure source and the super-chug will be represented by acceleration source.
The source terms (for normal and superchugs) thus developed will be used in an improved chugging load definition to be submitted to the staff in draft form in April 1981. These source tems w'ill also be used to gener- -
ate JAERI wall loads for comparison with the available JAERI data.'
!!. Improved CO Load Definition The applicant has not proposed CO load specifications for WNP-2; however, engineering evaluation of the 4TCO data indicate that fluid structure in-teraction are significant and when accounted for in the 4T system, signifi-cant reduction to the CO load will result.
III. SRV 1mproved load Definition The purpose of the meeting was to review the applicant's response to a number of questions related to the WPPSS-2 plant unique SRV discharge load methodology (see memorandum from E. Eltawila to W. R. Butler, dated
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September 18, 1980 for a summary ' description of the methodology). These questions were fonnally trancmitted to the LPM and informally to the ap-plicant by the Contaitsent Systeins Branch on December 19. 1980.
With one exception, the appl $r. ant's response: to our questf or.s were satis-factory. The information which was supplied ~in the fenu of handouts should suffice to clarify most of the issues and concerns raised by the staff and its coasultants, Additional revike of the riew informaticn is required, however, to decide shetner any of the questions can be eliminpted.
The exception mentioned above refers to the . issue of multiple valve actua-tion (MVA) effects. The applicant f adicated an unawareness that the Caorso inplant test data exhibited higher boundary loads during NVA tests than first actuation single valve actuations. This stems from their excluslye use of Sensor P19 to serve as an indicator of toundary load magnitudes. We suggested that it was more appropriate,particularly for MVA cases, to use the highest recorded values for test purposes, The applicant agreed with this position and stated its intent to re-examine the data base Jr1 this light.
1 One additional action item which the applicant intends to pursue is related to the vertical distribution of pressure amplitudes. (The applicaqt's ap-proach differs significantly from the existing DFTR methodology.) We ,
pointed out that the sensors from which the Caorso pressure data are obtained to demonstrate the adequacy of their proposed distribution are characterized by the General Electric Company (in the Caor50 test Report NEDE-24757-P) as being of poor accuracy. In view of this, the applicant intends to reanalyze these data and establish whether the reported poor accuracy will impact on their design specification.
Staff Comments The staff indicated that it did not envision a major review regarding the type of source to be used with the improved chugging Icad definition methodology. It appears from the applicant's presentation that a significant review of the type of source is needed. In addition, substantial comparison of results obtained using the developed source in the improved model with data from the multivent test facility (JAERI) and with data from another single vent test facility (GKM-!!M) will be necessary and will require additional reviev efforts.
The staff also indicated that, since the Mark II Owners Group is c.grrently in the process of establishing a generic chugging load specification, WPPSS should justify the need for plant unique review to the Director, Division of Gystems Integration. We have also indicated that if such plant unique review ms fcond to be necessary, our review will not begin before January 1982 due to the Severe manpower shortage. In addition, the staff and its consultant expressed concerns in the following:
m -
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FEE ? 1931 W. Butler ,
- 1) Revised Chugging Load Definition The need .to introduce a new type of chugging source, i.e., an acceler-ation pulse instead of a pressure pulse, to account for the large am-plitude chugs in the 4TCO tests is troublesome for several reasons:
a) it seems very difficult to accept on physical grounds, and if ac-cepted, would open many questions about the applicability of types of sources in general.
b) the stark difference in frequency response obtained from pressure versus acceleration pulses in the WPPSS 4T model is contrary to usual structural response experience, and suggests that the model-ing and entire methodology must be carefully examined to preclude any sort of built-in bias, c) verification o'f the methodology by comparison with JAERI data could be very difficult with the present axisymmetric model, i
- 2) Revised CO Load Definition The arguments presented were sketchy and based on very simplified analyses. It is difficult to believe the major effect attributed to FSI in the presentation since:
a) the arguments were neither complete nor convincing.
b) the particular 4TCO run chosen to present the case was not shown to be representative of C0 observations in general.
The contradictions between the conclusion drawn by WPPSS regarding the importance of FSI in CO and those stated in the generic Mark II C0 methodology need resolution by comparing data bases from facilities of differing stiffness such as GKM-II-M.
Wk Farouk Eltawila Containment Systems Branch Division of Systems Integration ec: D. Ross L. Rubenstein R. Tedesco ,
B. J. Youngblood D. Lynch R. Auluck J. Kudrick J. Lehner, BNL C. Economus, BNL
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