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Category:INTERNAL OR EXTERNAL MEMORANDUM
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 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 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 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 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 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 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 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 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 ML20214A5501987-05-14014 May 1987 Partially Deleted Memo Re Recommendation for Diablo Canyon Board Notification Concerning 831019 Allegations 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 ML20215H9221987-05-0707 May 1987 Submits Results of Lll Exam of Facility Raceway Support Bolted Connections.Exams Conducted Due to Allegations Re Adequacy of Anchor Bolts & Feedback from Lll That Adequacy of Bolting Might Be Safety Issue 1999-08-27
[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
[Table view] |
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- a 8,d[ 'o,, UNITED STATES o NUCL' EAR REGULATORY COMMISSION
{ ,g t)'a ,E WASHINGTON, D. C. 20555
- Q. '.& ..* /
MAR 4 1985 Docket No: 50-323 MEMORANDUM FOR: Thomas M. Novak, Assistant Director for Licensing Division of Licensing FROM: Robert J. Bosnak, Acting Assistant Director Components and Structures Engineering Division of Engineering
SUBJECT:
- EVALUATION OF ALLEGATIONS ON DIABLO CANYON UNITS 1 AND 2 The Mechanical Engineering Branch has evaluated the following assigned allegations: 1642 through 1646 and 1648. These evaluations are shown in the enclosure.
/
l Rober . Bosnak, Acting Assistant Director Components and Structures Engineering Division uf Engineering
Enclosures:
As $.ated cc: F herny
. Schierling, DL M. Ley, DL T. Sullivan, DE K. Manoly, R-I I
1
Contact:
M. Hartzman NRR Ext. 28445 ar_. fp.
Task: Allegation or Concern No. 1642 ATS No: BN No:
Characterization The most limiting combination of various piping loads were not always used as .c input for gang support calculations.
Implied Significance to Plant Design, Construction, or Operation If gang frames are not designed to the most. limiting load combinations an over-stress of member stresses and/or overload of supports / building interface could result. Depending on the magnitude of overload in the gang supports, an over-stress of safety related piping systems beyond code limits could result due to excessive deformation of supports.
Assessment of Safety Significance Based on audits performed at the San Francisco office of piping supports design and evaluation, overloads of gang pipe support frames are unlikely since:
- 1. Present project procedure considers numerous combinations of piping loads, such as thirty two load combinations in "STRUDL" analyzed single pipe supports and an adequate number of combinations for gang supports. These combinations include all plus and minus values of piping loads, and all plus values from some pipes and all minus values from other pipes.
- 2. Peak piping loads are asummed to occur simultaneously.
Staff Position The present PG&E project procedure for design and evaluation of gang pipe supports is considered adequate for determining the most limiting design condition. This allegation is considered resolved.
Action Required None..
Task: Allegation or Concern No. 1643 ATS No.: BN No:
Characterization Unusual structural components such as intermediate plates were not always .c analyzed because they appeared too complex.
Implied Significance to Plant Design, Construction, or Operation Potential overstress problems could exist when intermediate plates are use to connect pipe support members to building steel to facilitate welding.
Assessment of Safety Significance Safety significance would be in those cases where intermediate plates are used to connect two structural members of widely varying sizes. For those cases, a specific analysis is required to determine the plate thickness. PG&E response addressed this condition in a more general form.
Staff Position "
The content of the allegation is very broad and lacks specificity. The examples provided by the alleger (e.g., intermediate plates) didn't identify any specific cases of design deficiency. The staff considers the PG&E response to be adequate considering the generality of the allegation and consider this allegation resolved.
Action Required <g None.
1
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i -
Task: Allegation or Concern No.1644 ATS No.: BN No:
Characterization The weld stresses are not always analyzed for all weld configurations of a
- pipe support and were not always properly modeled. '
Implied Significance to Plant Design, Construction, or Operation Both concerns are applicable to pipe suppor.t design activity for safety 4
related piping systems. Improper weld design practices such as miscalculation i'
of weld properties or lack of consideration for governing load conditions could result in overstressing of weld beyond ' code limits, which could result, in some cases, in the failure of the support welds.
Assessment of Safety Significance
,, PG&E response which was confirmed by staff audit of pipe support design activities is as follows:
~
! 1. Welds were either modeled to conform to the actual configurations or to a more conservative: configuration in order to simplify the analysis.
Conservative configurations would have less weld than actual.
- 2. Analysis of worst case welds or the use of enveloped loads were done in lieu of performing an analysis for each case.
- Staff Position i PG&E response was determined to be acceptable and was confirmed by the review i of many pipe support design packages during the staff audits. This allegation is considered resolved.
Action Required None.
S
-,.--v.-----en,,n
Task: Allegation or Concern No. 1645 ATS No: BN No:
Characterization Flare bevel welds are not analyzed for shear in the base metal. .c Implied Significance to Plant, Construction, or Operation An overstress in the base metal is possible if the following two conditions exist at the same time. .
- 1. Effective throat thickness is e the base metal (at the fusion line) qual to the width of the weld connected to
- 2. Shear stress is equal to or greater than the normal stress, and the combined resultant stress is equal to the allowable stress value.
Assessment of Safety Significance The PG&E response addressing this concern indicated the followin%:
- 1. Effective throat size utilized in design is equal to 5/16R.
- 2. Project tests had demonstrated that actual effective throat in flare level welds was larger than 5/16R.
- 3. The likelihood of subjecting the welded connections to shear stresses higher than the 4 rmal stresses, and combined normal and shear stresses equal to the allo (nable limit is very low.
i Staff Position The above assessment is viable when considering other factors such as:
- 1. Treating flare bevel welds as partial penetration groove welds would account for much larger effective throat.
- 2. Weld lengths are usually rounded off to the nearest practical dimension.
When 611 of the above factors are considered, it can be reasonably assumed i that flare bevel welds are adequately proportioned for anticipated design loads. This allegation is considered resolved.
Action Required None.
k
Task: Allegation or Concern No. 1646 ATS No: BN No:
Characterization The design of pipe supports using wide flange beams or channels did not always .<
include the effects of torsion.
Implied Significance to Plant Design, Construction, or Operation Ignoring the effects of restrained torsion in the design of open sections of pipe support structural members could result in a significant increase of member stresses, particularly those related to warping normal stresses, when superimposed on the normal stresses induced by simple bending.
Assessment of Safety Significance This concern was addressed in item 7 of Licensing Condition 2.C.11 for Diablo Canyon Unit No. 1. These effects were also considered for Unit No. 2 in project instruction I-59, " Instruction for the evaluation of Licensing Condition No. 7-Concerns."
Staff Position The project instruction and its application in many pipe design packages were reviewed by the staff and were found to be acceptable. This allegation is considered resolved, t
Action Required None.
- 7. ----,------,-7--e,-------,-, - - - - - ,. + - - - -
o .
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Task: Allegation or Concern No. 1648 ATS No: BN No:
Characterization
- 1. Allowable stress values for lug attachments to piping may not be based .c on the maximum operating temperature of the pipe.
- 2. Stresses in welds may be underestimated due to improper weld geometry.
Implied Significan'ce to Plant Design, Construction, or Operation
- 1. Overstress of piping as a result of using a higher allowable stress than that corresponding to maximum operating temperature.
- 2. Overstress of welds stress on lugs attachments due to improper consideration of weld geometry.
Assessment of Safety Significance
- 1. Local stresses in piping at lug attachments are computed by 'Otilizing the forces and moments established from the applicable piping thermal- analysis results. The stress evaluation is accomplished using the computer code ME210, which which utilizes the formulations of Welding Research Council (WRC-Bulletin
- 107). The total stresses in the piping from primary, secondary and local stresses are evaluated to allowable limits obtained from ASME Code Case N-318
- for.the maximum operating pipe temperature.
- 2. Lug attachmengs to piping are typically oriented such that the lug length is parallel to the longitudinal axis of the pipe. This enables proper fillet or penetration weld between the lug and pipe wall.
Staff Position Based on the above, and on similar conclusions of the Independent Design Verification Program (IDVP) review of the same topic for Unit No. 1, it is concluded that lug attachments to piping are properly designed and evaluated.
This allegation is considered resolved.
Action Required None.
l f