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Category:BOARD NOTIFICATION (TO LICENSING BOARD OR LICENSING
MONTHYEARNUREG-1353, Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-13531989-05-0202 May 1989 Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-1353 NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants1989-02-14014 February 1989 Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants ML20215H9031983-10-27027 October 1983 Annotated Board Notification 83-164:forwards Allegations Re Certain Qa/Qc Activities.Source of Allegations Confidential. Related Documentation Encl ML20204G5401983-10-14014 October 1983 Board Notification 83-158:forwards Oct 1983 Sser 19 Re Matters Identified in Sser 18 & Listed in SECY-83-366,that Must Be Resolved Prior to Fuel Loading.Matters Adequately Resolved ML20151H4871983-05-0404 May 1983 Board Notification 83-057:forwards Differing Prof Opinions Re Sys Interaction & Safety Classification.Info Relates to Board Notifications 83-17 & 83-44 Re Unresolved Safety Issue A-17 ML20204F0461983-04-12012 April 1983 Board Notification 83-42:forwards Info Re Unanalyzed Reactor Vessel Thermal Stress During Cooldown.B&W Informed NRC of Preliminary Safety Concern Evolving from Further Consideration of 800610 St Lucie Upper Head Voiding Event ML20204F0361983-03-0404 March 1983 Board Notification 83-27:forwards 830221 Memo & Final Eg&G Rept Re Addl RELAP-5 Calculation for Semiscale S-SR-2 Test ML20244B9901983-01-0707 January 1983 Board Notification 83-03:notifies of Allegations Re Design Aspects of Component Cooling Water Sys Including Seismic Classification,Instrumentation & Control Design/ Classifications Approaches & Design of Generator Intakes ML20214K5091982-11-16016 November 1982 Board Notification 82-119:forwards Repts Re Design Verification Program - Phase I for Diablo Canyon Unit 1 ML20204F0161982-09-29029 September 1982 Board Notification 82-97:forwards Transcript of NRC 820909 Meeting W/State of CA Re Design Verification Program & Independent Design Verification Program:Auxiliary Bldg, Interim Technical Rept ML20204F0091982-09-24024 September 1982 Board Notification 82-93:forwards Addl Info Re Semiscale Test Results Concerning Feed & Bleed Mode of Core Cooling ML20214W7511982-08-19019 August 1982 Board Notification 82-89 Forwarding Transcript of NRC 820806 Meeting W/Util & Teledyne Engineering Svcs in Bethesda,Md Re Phase I of Facility Idvp.W/O Encl ML20213E2401982-08-12012 August 1982 Forwards Info Items Re Independent Design Verification program-Phase 1 (Idvp).Nrc Evaluating Info as Part of Ongoing Review of Idvp Efforts & Will Rept on Results Prior to Reinstatement of License.W/O Encl ML20204E9541982-06-18018 June 1982 Board Notification 82-60:forwarding Info Re Design Verification Program from Teledyne Engineering Svcs,Rl Cloud Associates,Inc & Rf Reedy,Inc ML20204E9511982-06-0404 June 1982 Board Notification 82-57:forwarding Info Re Status of Independent Design Verification Program Activities Relevant to Safety Issue on Design Adequacy.Results Will Be Reported Prior to Reinstatement of License ML20204E9381982-06-0202 June 1982 Board Notification 82-53:forwarding Summary of 820430 Discussion of Bechtel Rate in Completion of Project.Info Relevant to Design Adequacy Safety Issue ML20209B3661982-04-26026 April 1982 Board Notification 82-42 Forwarding Items Re Design Verification Program,Phase I for Facility.W/O Encl ML20212L2111982-03-24024 March 1982 Board Notification 82-29:forwards Listed Documents Re Seismic Design Adequacy of Facility ML20212L1871982-03-15015 March 1982 Board Notification 82-24:forwards W Cooper Re Design Verification Program Manager for Facility.W/O Encl. Related Info Encl ML20204E9331982-01-27027 January 1982 Board Notification 82-06 Forwarding Design Verification Program for Power Ascension:Diablo Canyon Nuclear Power Plant Unit 1, & Qualification Document - Design Verification Program for Power Ascension ML20151H1791982-01-20020 January 1982 Board Notification 82-04 Forwarding Info Re Pressurized Thermal Shock ML20204E9051981-11-0505 November 1981 Forwarding Draft Board Notification 81-38, Seismic Reverification Program Presented During 811103 Meeting W/ PG&E Re Current Status of Review & Evaluation of Seismic Discrepancies in Facility Containment Annulus Area 1989-05-02
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20211H4441999-08-27027 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 ML20196D7021999-06-25025 June 1999 Informs That Reactor Sys Branch Prepared Suppl 1 to GL 83-11 Re Licensee Qualification for Performing Safety Analyses, Which Was Issued on 990624.Matl Related to Subj GL Should Be Placed in PDR & Made Available to Public DD-99-05, Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action1999-04-20020 April 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action ML20205J2811999-04-0606 April 1999 Notification of 990422 Meeting for Dockets 7200026 & 7200027 with PG&E in Rockville,Md to Dicuss PG&E Plans for Dry Cask Storage at Humboldt Bay & Diablo Canyon IR 05000275/19993011999-03-25025 March 1999 Forwards NRC Operator Licensing Exam Repts 50-275/99-301 & 50-323/99-301 for Tests Administered on 990125-28 ML20205B2301999-03-25025 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990125-28 ML20207M3401999-03-0202 March 1999 Notification of Canceled Meeting Scheduled for 990309 Re 7200026 & 7200027 for PG&E Plans for Dry Cask Storage at Humboldt Bay & Diablo Canyon ML20155H9051998-11-0303 November 1998 Notification of 981117 Meeting for Dockets 7200026 & 7200027 with Util in Rockville,Md to Discuss PG&E Plans for Dry Cask Storage ML20248K4451998-06-0202 June 1998 Notification of 980617 Meeting W/Util in Rockville,Md to Discuss PG&E Plans for Dry Cask Storage.Meeting Agenda Encl ML20247G9081998-04-0707 April 1998 Discusses Experts Needed for Plant Life Extension Cases,Per 980403 Discussion ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20134P2231997-02-20020 February 1997 Discusses Ti 2515/122 Evaluation or Rosemount Pressure Transmitter Performance & Licensee Enhanced Surveillance Programs multi-plant Action B-122 NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20134B5061994-04-13013 April 1994 Submits Plants Which Will Be Discussed in Categories Indicated Re Results of Screening Meetings for June 1994. Partially Deleted ML20057A9941993-09-14014 September 1993 Forwards NRC Proposed Transcript Corrections ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20127P4161993-01-19019 January 1993 Provides Summary of 930113 Operators Reactors Events Briefing.List of Attendees & Viewgraphs of Elements Discussed Encl ML20126F0201992-12-16016 December 1992 Discusses Discrepancies in Svcs Rendered for 3rd & 4th Quarters of 1991 & 1st,2nd & 3rd Quarters of 1992.TLD Program for Humbolt Bay Site Did Not Strictly Follow Ltr of Contract ML20127D4321992-09-0101 September 1992 Forwards 920818 Petition Submitted by N Culver on Behalf of San Luis Obispo Mothers for Peace,Filed in Response to NRC Notice of Issuance of Amend to Licenses for Plant,Extending Expiration Date from 080423 to 210922 ML20058P5021990-08-15015 August 1990 Forwards Three Analyses of Shutdown Events Evaluated by Accident Sequence Precursor Program ML20247M1881989-05-26026 May 1989 Notification of 890613,14 & 15 Meetings W/Util in San Francisco,Ca to Discuss PRA Topics Re NRC Questions on long-term Seismic Program NUREG-1353, Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-13531989-05-0202 May 1989 Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-1353 NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants1989-02-14014 February 1989 Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants ML20154E5121988-05-0909 May 1988 Requests That Zip Code for Judge Es Bowers Address Be Changed as Stated,Per Iw Smith Request.Related Correspondence ML20153E3031988-05-0303 May 1988 Forwards NRR Input to Status of Regulatory Activities at Plants,In Response to J Curtis Request for Info ML20153E3381988-04-21021 April 1988 Requests Input on Status of Regulatory Activities for Listed Plants,Status of EPRI Research for RES & Status of California Low Level Waste Program.Response Requested by 880505 ML20151D4271988-03-24024 March 1988 Submits Summary of Actions Discussed at ACRS 335th Meeting on 880310-12 in Washington,Dc,Including ACRS Repts/ Recommendations,Other Actions,Agreements,Assignments & Requests & Future Agenda ML20148G2281988-03-22022 March 1988 Advises That Time for Commission to Review Naslap Decision (ALAB-880) Expired.Commission Declined Review.Decision Became Final Agency Action on 880318.Served on 880323 ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20236Y1501987-12-0707 December 1987 Staff Requirements Memo Re 871125 Affirmation/Discussion & Vote.Commission Approved Order Directing Aslab to Issue Decision by 880131 Re Installation of high-density Spent Fuel Racks & Order Vacating Stay for Low Power Operations ML20236R7551987-11-20020 November 1987 Informs That Time Provided by NRC Regulations within Which Commission May Act to Review ALAB-877 Expired.Commission Declined Review.Decision Became Final Agency Action on 871117.Served on 871120 ML20236N8421987-11-12012 November 1987 Documents Reconstitution of Aslab for OL Amend Proceeding to Consist of as Rosenthal,Cn Kohl & Ha Wilber.Related Correspondence ML20236H2821987-10-30030 October 1987 Informs That Time Provided within Which Commission May Act to Review ALAB-873 Expired.Commission Declined Review. Decision Became Final Agency Action on 871028.Served on 871102 ML20235H6291987-09-25025 September 1987 Informs of Reconstitution of Aslab Consisting of Author as Chairman & TS Moore & Ha Wilber as Members ML20234F3831987-09-14014 September 1987 Documents Results of Exam of Bolted Connections of Raceway Supports at Plant.Exam Conducted Due to Allegations Received Re Adequacy of Anchor Bolts Securing Raceway Supports to Concrete ML20238A6481987-08-17017 August 1987 Forwards Page 7 of 870813 Pleading Entitled, Response of NRC Staff to Licensing Board Order of 870732 (Directing Parties to File Comments on Applicability of Appeal Boards Decision...), Which Was Inadvertently Omitted ML20195F8261987-08-0707 August 1987 Forwards Listed Data Tables for Use in Preparing Performance Analyses for Plant,Per DF Kirsch 870728 Memo.Salp Performance Analyses Should Be Submitted to J Burdoin by 870825 ML20235M1861987-07-13013 July 1987 Forwards Complete Footnote 5 as Appearing on Pages 8 & 9 of 870710 Answer to Sierra Club Motion to Admit Contention Re Generic Issue 82 & to Direct Preparation of Eis. Due to Quirk in Programming,Not All of Footnote 5 Printed ML20235G5441987-07-0808 July 1987 Forwards NRC Staff Proposed Findings of Fact & Conclusions of Law in Form of Initial Decision Re Licensee Amend Request to Expand Spent Fuel Pools at Plant ML20234F5101987-07-0606 July 1987 Informs of Large Number of Limited Appearance Statements Filed in Proceeding.Documents Will Not Be Served,Per Board Chairman Discussions.Documents Will Be Made Part of Official Record & Will Be Available for Insp.Served on 870706 ML20216D0931987-06-22022 June 1987 Forwards Transcript Pages 65-68 of J Mcdermott Limited Appearance Statement on 870615 Re Defective Weld at Plant Approved by QC Inspector for Appropriate Action.Served on 870624 ML20214W5681987-06-0505 June 1987 Forwards List of Exhibits Intended to Be Offered by Sierra Club in Upcoming Hearing in Proceeding Re Spent Fuel Pool. List Received Too Late for Inclusion in to ASLB ML20214T2031987-06-0505 June 1987 Forwards NRC Staff Disk in Ascii Form,Containing Staff Testimony & Draft Proposed Findings of Fact & Conclusions of Law,Per ASLB 870522 Memorandum & Order.Requests Database Compiled by ASLB Be Provided on Encl Blank Disks ML20214T1581987-06-0404 June 1987 Forwards NRC Staff Testimony of Hg Ashar,Hm Fishman,G Degrassi,Wl Brooks & a Singn on Sierra Club Contentions I(A)3 & 4;I(B)2,8 & 9;II(A)1-9 & II(B)1-9 & Dp Cleary on Sierra Club Contention I(B)7,per ASLB 870128 & 0409 Orders ML20214T2251987-06-0303 June 1987 Confirms 870602 Telcon Informing ASLB of Staff Intention to Offer Listed Documents as Staff Exhibits in Upcoming Hearing on Spent Fuel Pool ML20195G2301987-06-0202 June 1987 Discusses Plans for Response to Lessons Learned from Plant 870410 Loss of RHR Event.Crgr Review of 50.54(f) Ltr Providing Addl Info Requested at Earliest Opportunity ML20149M6491987-05-29029 May 1987 Forwards Proposed 10CFR50.54(f) Ltr Currently Being Reviewed for Transmittal to CRGR on 870602.Comments,if Necessary, Requested by 870601 ML20214L5831987-05-21021 May 1987 Summarizes 870519 Operating Reactors Events Meeting 87-15 to Brief Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events Which Occurred Since 870512 Meeting.Events Discussed & Significant Elements of Events Encl ML20245B1911987-05-18018 May 1987 Presents Composite Set of NRC & Industry Recommended Remedial Actions Based on 1985 AEOD Case Study Rept C503 Re DHR Problems for PWR Operation.Table 1 Presenting Chronology of 37 events,cost-benefit Analysis & Related Info Encl IA-87-714, Presents Composite Set of NRC & Industry Recommended Remedial Actions Based on 1985 AEOD Case Study Rept C503 Re DHR Problems for PWR Operation.Table 1 Presenting Chronology of 37 events,cost-benefit Analysis & Related Info Encl1987-05-18018 May 1987 Presents Composite Set of NRC & Industry Recommended Remedial Actions Based on 1985 AEOD Case Study Rept C503 Re DHR Problems for PWR Operation.Table 1 Presenting Chronology of 37 events,cost-benefit Analysis & Related Info Encl 1999-08-27
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Docket No. 50-275 MEMORANDlN FOR: Chairman Palladino Commissioner Gilinsky Comissioner Ahearne Comissioner Roberts Comissioner Asselstine FROM: Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation *
SUBJECT:
INFOR!% TION ITEMS REGARDING THE DESIGN VERIFICATION PROGRAM - PHASE I FOR DIABLO CANYON, UNIT 1 (Board Notification No'. 82 )
In accordance with present NRC procedures for Board Notifications, the following is enclosed for information to the Comission:
Transcript of NRC Meetirg with Pacific Gas & Electric and Teledyne Engineering Service on August 6,1982, in Bethesda, Maryland.
The enclosure is a verbatim transcript of a meeting at which Pacific Gas & Electric (PG&E) discussed the scope, status and schedule of its Internal Technical Program (ITP) and the relationship of the program to the Independent Design Verification Program (IDVP) under the management of Teledyne Engineering Services (TES). PG&E discussed its ongoing corrective action program which responds to error or open items (E01s) that have been identified throup the IDVP and the ITP. This corrective action program includes a seismic analysis of all safety-related structures, a verification of all large bcre safety-related piping, including support analysis, and complete rearalysi: of small bore piping where required. PG&E stated that work-packages will os issued for completed elements of the corrective action program which will be available for audit. PG&E presented an overall schedule for the design verification effort which calls for fuel loading by the end of Noverter 1982. PG&E was requested by the staff to prepare a list of all safety-related structures, systems and components that are required for fuel loading. W. Cooper, Teledyne Project Manager of the IDVP, briefly summarized the status of the program.
Representatives of the Joint In ervenors and of the Governor of the State of California made brief statements at the end of the meeting. All parties agreed that another meeting should take place as early as possible (late August-early September) to discuss the status of various technical and programmatic issues.
Contact:
Hans Schieri fng, ONRR X27238 N
8612100388 861205 PDR FOIA HOL;9586-151 PDR -
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' The Comission '
The submittIO provides information on the status of the Independent Design Verification Program activities for Diablo Canyon Unit 1. The information is relevant to the subject of Comission adequacy of Diablo Canyon Unit 1.
This is the subject of Comission Order CLI-81-30 which is the basis for the IDVP. The staff is evaluating the infomation aspart of its ongoing review of the IDVP efforts and will report on the results prior to reinstatement of the license. The material does not pertain to those matters that were resolved by ALAB 644. ,
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-;(kb$bf/[b(MLL Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Encl osure:
As stated cc: ASLB ASLABP
-SECY OGC OPE
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t BDARD NOTIFICATION 82-Diablo Canyon IDVP - Transcript of August 6 Meeting with NRC, TES and FG&E Distribution (*w/ enclosure)
Document Control (50-275)
NRC PDR L PDR PRC System NSIC LB#3 Reading
- F. Miraglia J. Lee H. Schierling * ,
T. Novak/J. Kerrigan/L. Berry D. Eisenhut/R. Purple M. Williams H. Denton/E. Case
- PPAS J. Youngblood A. Schwencer E. Adensam H. Bernard R. Mattson R. Vollmer H. Thompson S. Hanauer Attorney, OELD*
W. J. Dircks, ED0 (3)
E. Chris tenbury , OELD*
J. Scinto, OELD*
A. Bennett, OELD (3)*
cc: Board Service List Licensee Service List
S'. ,,
I Docket No. 50-275; - '
MEPORANDIN FOR: Diairnan Palladino Comissioner Gilinsky Comissioner Ahearne Comissioner Roberts Comissioner Asselstine FROM: Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
SUBJECT:
INFORi% TION ITDiS REGARDING THE DESIGN VERIFICATION PROGRAM - PHASE I FOR OIABLO CANYON, UNIT 1 (Board Notification No'. 82- 89 )
In accordance with present NRC procedures for Board Notifications, the folicwing is enclosed for information to the Comission:
Transcript of NRC fleeting with Pacific Gas & Electric and Teledyne Engineering Service on August 6,1982, in Bethesda, Maryland.
The enclosure is a vernatim transcript of a meeting at which Pacific Gas & Electric (PGt.E) discussed the scope, status ar.d schedule of its Internal Technical Pmgram (ITP) and the relationship of the program to under the management theTeledyne of Independent Engineering Design Services Verification (TES). PG&E Program disc (IDVP)'ussed its ongoing corrective action program which responds to error or open items (E01s) that have been identified through the IDVP and the ITP. This corrective action pmgran includes a seismic analysis of all safety-related structures, a verification of all large bore safety-related piping, including support analysis, and complete reanalysis of small bore piping where required. PG&E stated that work-packages will be issued for completed elements of the corrective action program which will be available for audit. PG&E presented an overall schedule for the design verification effort which calls for fuel loading by the end of November 1982. PG&E was requested by the staff to pmpare a list of all safety-related structures, systems and components that are mquired for fuel loading. W. Cooper Teledyne Project Manager of the IDVP, briefly summarized the status of the program.
Representatives of the Joint Intervenors and of the Governor of the State of California made brief statements at the end of the meeting. All parties
' agreed that another meeting should take place as early as possible (late August-early September) to discuss the status of various technical and pmgramatic issues.
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The Comission '.
The submittal provides infonnation on the status of the Independent Design Verification Program activities for Diablo Canyon Unit 1. The information is relevant to the subject of Commission adequacy of Diablo Canyon Unit 1.
This is the subject of Comission Order CLI-81-30 which is the basis for the IDVP. The staff is evaluating the infonnation aspart of its ongoing review of the IDVP efforts and will report on the results prior to reinstatement of the license. The r:aterial does not pertain to those matters that were resolved by ALAB 644.
N I G 3 E M .h Darrell G. Eisenhut, Director Division of Licensing Offi<:e of Nuclear Reactor Regulation
Enclosure:
As stated cc: ASLB ASLABP SECY OGC OPE DISTRIBUTION See attached
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