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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20205B6111999-03-26026 March 1999 Notification of 990419 Meeting with Util in Rockville,Md to Discuss Licensing Issues at Plant,Including Racking of Cask Pit for Storage of Spent Fuel ML20153F7981998-09-23023 September 1998 Forwards NRC Operator Licensing Exam Rept 50-346/98-301OL, (Including Completed & Graded Tests) for Tests Administered on 980803-07 ML20153F8291998-09-23023 September 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered During Wk of 980803 ML20236F3581998-06-26026 June 1998 Forwards NRC Insp Mc 0350, Staff Guidelines for Restart Approval, for Oversight Activities for Davis Besse Station ML20236N8641998-06-11011 June 1998 Discusses TS Interpretation on Application of Davis Besse TS 3.6.5.1 & 3.6.5.2.TB Branch Recommends That Davis Besse Consider Converting TS to Improved Standard TS ML20216F3291998-04-13013 April 1998 Accepts 980406 Licensee Request for Approval to Install machine-welded SG Tube Plugs in Accordance W/Provisions of Paragraph IWB-4230, Tube or Tubesheet Hole Plugging by Fusion Welding, of Section XI ML20202E6241997-11-26026 November 1997 Notification of 971215 Meeting W/Util in Rockville,Md to Discuss Quality Assurance Program at Davis-Besse ML20211Q4711997-10-16016 October 1997 Notification of 971113 Meeting W/Toledo Edison Co in Rockville,Md to Discuss Ultimate Heat Sink at Davis-Besse ML20211B5561997-09-23023 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970707-11 ML20211C5091997-09-23023 September 1997 Forwards NRC Operator Licensing Exam Rept 50-346/97-308OL (Including as-given Writtem Exam) for Tests Administered on 970707-10 ML20149E7411997-07-16016 July 1997 Notification of 970821 Meeting W/Util in Rockville,Md to Discuss Instrument Drift Study ML20137U2051997-04-14014 April 1997 Informs That Davis-Besse Nuclear Power Station Nuclear Assurance Dept Will Be Reorganized Into Two Separate Dept; DB Nuclear Assurance & DB Nuclear Support Svc,Effective, 970414 ML20136F9491997-03-13013 March 1997 Notification of 970403 Meeting W/Util in Rockville,Md to Discuss Progress on Thermo-Lag Issue Resolution ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20134P9011996-11-26026 November 1996 Notification of 961204 Meeting W/Clei & Teco in Rockville,Md to Discuss Potential Submittals Concerning Proposed Merger of Centerior Energy Co & Oec ML20149E8161994-08-0202 August 1994 Forwards Fr Notice of License Amend Requests Proposed Merger of Toledo Edison Co & Cleveland Electric Illumianting Co Antitrust Determination ML20059H8361994-01-19019 January 1994 Notification of 940201 Meeting W/Util in Rockville,Md to Discuss Pending Davis-Besse Licensing Actions ML20057F1311993-10-0707 October 1993 Notification of 931020 Meeting W/Util in Rockville,Md to Discuss Davis-Besse Implementation of Reg Guide 1.97 for Steam Generator Pressure Instruments ML20127N6121993-01-25025 January 1993 Notification of 920205 Meeting W/Util in Rockville,Md to Discuss Emergency Action Levels Proposed Rev,Submitted 930112 ML20127C0411993-01-0808 January 1993 Notification of 930112 Meeting W/B&W Owners Group in Clearwater Beach,Fl to Discuss Generic Program Plan for License Renewal Initiative ML20127F5461993-01-0707 January 1993 Notification of 930115 Meeting W/Util in Rockville,Md to Discuss Plant Containment Penetration Bellows Tests.Draft Agenda Encl ML20126F5541992-12-0808 December 1992 Notification of 921215 Meeting W/Util in Rockville,Md to Discuss Proposed License Amend to Change from Automatic to Manual Closure of Containment Purge & Exhaust Valves in Mode 6 ML20128C2071992-11-0606 November 1992 Notification of 921202 Meeting W/Util in Rockville,Md to Discuss Upcoming Refueling Outage Plans & Recent Plant Performance ML20127C4131992-07-24024 July 1992 Responds to 910322 Memo Requesting Assistance on Whether 10CFR50.59 Review Should Have Been Performed for Broken Pipe in Station Drainage & Discharge Sys Releasing low-level Radioactivity Onsite ML20059D2711990-08-0606 August 1990 Discusses Review of State of Oh & Local Radiological Emergency Response Plans.Determined That No Issues Identified During 890809-09 Exercise to Prevent Finding of Reasonable Assurance for Site ML20148T1891990-04-10010 April 1990 Responds to Request for Info Re Congressional Inquiries on Tracking & Closeout of Issues Raised Re Incident Investigation Team (IIT) Investigations of Plants.Actions Assigned by EDO in Response to Plant IITs Addressed ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20246N8091989-08-30030 August 1989 Notification of 890907 Meeting W/Util in Rockville,Md to Discuss Exemption from App R to 10CFR50 for Specific Configuration of Pressurizer Instrumentation ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20244A4611989-06-0606 June 1989 Notification of 890615 Meeting W/Util & Westinghouse Owners Group in Rockville,Md to Discuss Reactor Vessel Support Embrittlement ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) 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 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 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 ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20244A5571989-04-10010 April 1989 Notification of 890502 Meeting W/Util in Rockville,Md to Discuss Nonlinear Piping Analysis to Remove Snubbers & Pipe Supports ML20244A5461989-04-10010 April 1989 Notification of 890503 Meeting W/Util in Rockville,Md to Discuss Using Leak Before Break Methodology on Lines Connected to RCS 1999-03-26
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20205B6111999-03-26026 March 1999 Notification of 990419 Meeting with Util in Rockville,Md to Discuss Licensing Issues at Plant,Including Racking of Cask Pit for Storage of Spent Fuel ML20153F7981998-09-23023 September 1998 Forwards NRC Operator Licensing Exam Rept 50-346/98-301OL, (Including Completed & Graded Tests) for Tests Administered on 980803-07 ML20153F8291998-09-23023 September 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered During Wk of 980803 ML20236F3581998-06-26026 June 1998 Forwards NRC Insp Mc 0350, Staff Guidelines for Restart Approval, for Oversight Activities for Davis Besse Station ML20236N8641998-06-11011 June 1998 Discusses TS Interpretation on Application of Davis Besse TS 3.6.5.1 & 3.6.5.2.TB Branch Recommends That Davis Besse Consider Converting TS to Improved Standard TS ML20216F3291998-04-13013 April 1998 Accepts 980406 Licensee Request for Approval to Install machine-welded SG Tube Plugs in Accordance W/Provisions of Paragraph IWB-4230, Tube or Tubesheet Hole Plugging by Fusion Welding, of Section XI ML20202E6241997-11-26026 November 1997 Notification of 971215 Meeting W/Util in Rockville,Md to Discuss Quality Assurance Program at Davis-Besse ML20211Q4711997-10-16016 October 1997 Notification of 971113 Meeting W/Toledo Edison Co in Rockville,Md to Discuss Ultimate Heat Sink at Davis-Besse ML20211C5091997-09-23023 September 1997 Forwards NRC Operator Licensing Exam Rept 50-346/97-308OL (Including as-given Writtem Exam) for Tests Administered on 970707-10 ML20211B5561997-09-23023 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970707-11 ML20149E7411997-07-16016 July 1997 Notification of 970821 Meeting W/Util in Rockville,Md to Discuss Instrument Drift Study ML20137U2051997-04-14014 April 1997 Informs That Davis-Besse Nuclear Power Station Nuclear Assurance Dept Will Be Reorganized Into Two Separate Dept; DB Nuclear Assurance & DB Nuclear Support Svc,Effective, 970414 ML20136F9491997-03-13013 March 1997 Notification of 970403 Meeting W/Util in Rockville,Md to Discuss Progress on Thermo-Lag Issue Resolution ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20134P9011996-11-26026 November 1996 Notification of 961204 Meeting W/Clei & Teco in Rockville,Md to Discuss Potential Submittals Concerning Proposed Merger of Centerior Energy Co & Oec ML20149E8161994-08-0202 August 1994 Forwards Fr Notice of License Amend Requests Proposed Merger of Toledo Edison Co & Cleveland Electric Illumianting Co Antitrust Determination ML20059H8361994-01-19019 January 1994 Notification of 940201 Meeting W/Util in Rockville,Md to Discuss Pending Davis-Besse Licensing Actions ML20057F1311993-10-0707 October 1993 Notification of 931020 Meeting W/Util in Rockville,Md to Discuss Davis-Besse Implementation of Reg Guide 1.97 for Steam Generator Pressure Instruments ML20127N6121993-01-25025 January 1993 Notification of 920205 Meeting W/Util in Rockville,Md to Discuss Emergency Action Levels Proposed Rev,Submitted 930112 ML20127C0411993-01-0808 January 1993 Notification of 930112 Meeting W/B&W Owners Group in Clearwater Beach,Fl to Discuss Generic Program Plan for License Renewal Initiative ML20127F5461993-01-0707 January 1993 Notification of 930115 Meeting W/Util in Rockville,Md to Discuss Plant Containment Penetration Bellows Tests.Draft Agenda Encl ML20126F5541992-12-0808 December 1992 Notification of 921215 Meeting W/Util in Rockville,Md to Discuss Proposed License Amend to Change from Automatic to Manual Closure of Containment Purge & Exhaust Valves in Mode 6 ML20128C2071992-11-0606 November 1992 Notification of 921202 Meeting W/Util in Rockville,Md to Discuss Upcoming Refueling Outage Plans & Recent Plant Performance ML20127C4131992-07-24024 July 1992 Responds to 910322 Memo Requesting Assistance on Whether 10CFR50.59 Review Should Have Been Performed for Broken Pipe in Station Drainage & Discharge Sys Releasing low-level Radioactivity Onsite ML20059D2711990-08-0606 August 1990 Discusses Review of State of Oh & Local Radiological Emergency Response Plans.Determined That No Issues Identified During 890809-09 Exercise to Prevent Finding of Reasonable Assurance for Site ML20148T1891990-04-10010 April 1990 Responds to Request for Info Re Congressional Inquiries on Tracking & Closeout of Issues Raised Re Incident Investigation Team (IIT) Investigations of Plants.Actions Assigned by EDO in Response to Plant IITs Addressed ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20246N8091989-08-30030 August 1989 Notification of 890907 Meeting W/Util in Rockville,Md to Discuss Exemption from App R to 10CFR50 for Specific Configuration of Pressurizer Instrumentation ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246D8841989-06-19019 June 1989 Staff Requirements Memo Re 890601 Briefing on Operating Reactors & Fuel Facilities in Rockville,Md.Commission Expressed Disappointment in Long Term Operating Performance of Turkey Point Nuclear Power Plant ML20244A4611989-06-0606 June 1989 Notification of 890615 Meeting W/Util & Westinghouse Owners Group in Rockville,Md to Discuss Reactor Vessel Support Embrittlement ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl 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 ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) 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 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 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 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 ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl 1999-03-26
[Table view] |
Text
.
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n January 4, 1979 ,,
ACDS MPGERS DAVIS-BPSSE 1 SEISMIC MARGItG
'Ihe attached write up was prepared in February 1977 at the time of Mr. Froley's letter of clarification on ACRS Davis Besse 1 report.
' It has been brotryht up to date and should provide the background information on Davis Fesse that you requested.
R. L. Wright Staff Enginaer
Attachment:
As State '
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! e508230089 850722 PDR FOIA I DELLOS-363 PDR 0l/J' orrie s
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I-4-79 NRC PORM 313 (9 76) NRCM 0240 N u. s. aovammusur rnieno orrecas tere -em L .T M .
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2 BACEROLMD INFORMATION REGARDIC 1HE RE0thEST FOR INTERPRETATION -
.OP THE COMMITTEE'S OL LE' ITER 09 DAVIS BESSE UNIT 1 REIATING 1D SEISMIC DESIGN MARGIN Using procedures in effect at the time of the CP application (1969) the Toledo Edison Company established an SSE value of 0.15g at the i foundation level and an OBE of 0.08g. % e 0.15g was applied at the
! foundation with spectra modified from the Helena earthquake of 1935.
I Wis spectra is less conservative than used now, but danping factors
- are about 1/2 of those used now. At the CP stage the NRC Staff accepted these values and also the selection of the naximum possible earthquake (medim MM VII) . In October 1974, the NRC Staff changed their procedures for establishing the SSE value. % is procedure involves the tectonic approach to arrive at an intensity value at the site.
- Trifunac-Brady curves (best fit) are then used to relate-intensity to acceleration. %e acceleration value is then used for the Reg. Guide I
1.60 Spectrun and is applied at finished grade in the free field. Wis j is then deconvoluted to foundation level for deep and sometimes meditra
- depth soil sites. (Tr 46 201st Meetirvj) . Fb11owing the procedures now in effect would yield an SSE of 0.20g at the ground surface in free l field as the scismic criteria for the Davis Besse Site. Deconvolution i would not be applied to Davis Besse. i At the Subcommittee meeting (December 21, 1976) the only mention of seismic i design was a statenont by the NRC Project Manager (Leon Engle) that the ;
i seismicity of the Davis Besse Site is being evaluated by the EC Staff I and there nay be a Staff difference in opinion in the final Staff position..
l %is apparently related to Mr. Rider's opinion that a 0.25g SSE value l' should be used at a site such as Davis Besse in the central stable region.',
Mr.' Rider nade a presentation on this to the Committee at the January 1977 meeting (Tr 51, 201st Meeting).
- 1 l On December 15, 1976, the NRC Staff infomed Toledo Edison that they might i' j impose 0.29 at the ground surface in the free field. About a day or two before the January 1977 full Co9mittee neeting, the NRC Staff decided not , %;
to impose this 0.29 value on Davis Eesse 1; they were satisfied with the ' dN I 0.15g at the foundation level. W e NRC Staff reported this to the full Committee during- the Davis Besse 1 review at the January 1977 Committee
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meeting. Se NRC Staff did, however, inform the Applicant that they
, would impose the 0.29 free field value as the seismic criteria for Davis j Besse 2 arri 3. At the January 1977 meeting, Harold Denton said that since q l the Sumer of 1976, the NRC Staff has consistently applied acceleration j at the ground surface in free field, and that the computer code SimKE is used to derive data for the foundation of each building. He said that :
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l . . . . . . l i NRC PORM Me (9 76) NRCM 0240 W u. s.oovsamusar pasarine orrecss so7e-aseene
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. V during'the preceeding two years (1974-76) the deconvolution was not used except on a few plants.
I At the full Connittee neeting in Jantary 1977, the Applicant stated that there is about 25 to 35 feet of compacted soil material to which
- a deconvolution process can be applied. We Applicant stated that pre-lininary calculations deconvoluting a . 0.29 through the 25-35 feet of soil to the foundation results in a g- value of about 0.16. We Connit-i tee (Dr. Siess and Dr. Okrent in particUlar) does not seen to be con-fident as to the justification and procedure for the deconvolution pro-l cess. %c NRC Staff stated that reevaluation of the selsnic design of
. the plant had not been done, and they implied that a process of exper-ience and judgment went into their decision not to impose the 0.29 free field value. Dr. Okrent pinted out that the North Anna Subconnittee f had asked for an analysis of the safety margins of all safety-related systens under SSE conditions. At the ! brth Anna Subcommittee meeting
. the Applicant gave sone examples, but apparently did not know values for all safety-related syntems. We Comittee put the same reconnendation in the North Anna and Davis.Besse letters regarding an NRC staff review of the SSE design and prestnably for the sane reasons. bledo Edison Muhaitted a preliminary reyrt on January 27, 1977 on their seisnic design l review.
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i omcu p f summaus k o'ats > . . .
I' feo PGM( Me (9 749 NRCM 0340
- un e. novsmuusur enenvine orrecs, sore - one.ea4
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