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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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- . UNIT ED S TATES 8 \;'3, h NUCLEAR REGULATORY COMMISSION 5 -- %j g~.:-, . ,g REGION lli
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July 10, 1984 MEMORANDUM FOR: Richard H. Vollmer, Director, Division of Engineering, Nuclear Reactor Regulation FROM: I. T. Yin, Senior Mechanical Engineer, Division of Reactor Safety, Region III
SUBJECT:
COMMENTS ON SSER LICENSE CONDITION 2.C.(11) PREPARED BY THE DIABLO CANYON PIPING PEER REVIEW PANEL The draft SSER License Condition 2.C.(11) Items 1, 4, 5, 6, and 7 were telecopied to Region III on July 3,1984. Items 2 and 3 were received o'n July 9, 1984. Provided herewith are my comments.
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I.' T. Yin Senior Mechanical Engineer Division of Reactor Safety Region III 8609190305 860916 PDR FOIA HOLMES86-197 PDR
SSER for License Condition 2.C.(11), Item 1 PG&E shall complete the review of all small bore piping supports which were reanalyzed and requalified by computer analysis. The review shall include consideration of the additional technical topics, as appropriate, contained in License Condition No. 7 below.
Comments The following data is required before any meaningful comments can be provided:
- 1. Subsequent to the OCP's review of all computer analyzed small bore piping supports, how many (among the 358 total population) will require hardware adjustment, modification or rework?
- 2. In conjunction with 1 above, how many were unable to meet the Code and FSAR requirements after the first rerun in the computer?
These supports required alternative or additional computational effort in orde'r to meet the design criteria.
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- 3. Peer Review Panel (PRP) identified that OPEG design judgement (design
. basis and criteria presumably) was not documented in some of the calculations. What PRP action,.if any, was initiated to determine that these were just a few isolated cases? If the situation was determined to be generic, was there any license program upgrade mandated by the PRP?
- 4. PRP identified calculational deficiencies consisting of erroneous STRUDL input assumptions of structural member properties and geometry. Was there a licensee procedure that had included avantitative or cualitative acceptance criteria for accepting these types of deficiencies?
If not,'what are the PRP's criteria in determining that no further action is reauired?
SSER for License Condition 2.C.(11), Item 2 The licensee shall identify all cases in which rigid supports are placed in close proximity to other rigid supports or anchors. For these cases, the lic-ensee shall conduct a program that assures loads shared between these adiacent supports and anchors result in acceptable piping and support stresses. Upon completion of this effort, the licensee shall submit a report to the NRC staff documenting the results of the program.
Comments
- 1. The SD and 10D criteria was established by Peer Review Panel (PRP) on June 20, 1984 at Cloud office with my concurrence. One week later the NRR staff telephoned me stating that the licensee had requested some exemption on the 100 proximity criteria for the snubber-anchor pair.
Decoupled branch connections designed by the span rule were requested to be excluded for the review because it will require excessive effort, and that may delay licensing process. The NRR staff honored the reouest based on. the reason that the decoupling branch connections are less important to safety. Plesse .p'rovide tectinical justification on exempting .
the PRP criteria. 'I reme.mber clearly. that.Dr. Cloud had stated, during various hearings and meetings, that the only small bore piping that will be overstressed during seismic event would be those located at the connections to the large bore piping.
- 2. The SSER states, "If unacceptable, the actual manufacturer's test reports on lost motion were reviewed for the unique snubber." Please explain why snubber displacements under load were not a concern to the PRP in deter-mining snubber operability?
- 3. The SSER stated, "The plant site inspection provided the NRC staff (PRP presumably) an opportunity to inspect the affected components on a first hand basis.", and that three snubbers installed in proximity to the equipment nozzle and rigid restraints "were viewed" by PRP. Please discuss the purpose and scope of the viewing, and what hardware attri-butes had been checked and verified by PRP.
- 4. Among the 95 " proximity" snubbers, please provide the following technical information:
Cr hiere
- a. Install tion of the snubber is iustified because of excessive (1/16" thermal movement at the location. How many belong in this category?
- b. How many snubbers, subsequent to the evaluation, were determined to be inoperable at either DE, DDE, or Hosgri seismic condition based on the 0.06" deflection criteria?
SSER for License Cnndition 2.C.(11), Item 3 The licensee shall identify all cases in which snubbers are placed in close proximity to rigid supports and anchnrs. For these cases, utilizing snubber lockup motion criteria acceptable to the staff, the licensee shall demon- ,
strate that acceptable piping and piping support stresses are met. Upon '
completion of this effort, the licensee shall submit a report to the NRC staff documenting the results. .
Comments
- 1. The SD and 10D criteria was established by Peer Review Panel (PRP) on June 20, 1984 at Cloud office with my concurrence. One week later the NRR staff telephoned me stating that the licensee had requested some exemption on the 100 proximity criteria for the restraint-anchor pair.
Decoupled branch connections designed by the span rule were requested to be excluded for the review because it will require excessive effort, and that may delay licensing process. The NRR staff honored the request based on the reason that the decoupling branch conne'ctions are less important tol safety. Please provide technical justifiyation.on exempting:
the PRP criteria. 'I remember clearly that Dr. Cloud had stated, during- -
various hearings and meetings, that the only small bore piping that will- -
be overstressed during seismic event would be those located at the '
connections to the large bore piping.
- 2. Among the 423 rigid restraints, how many required shimming?
- 3. In conjunction with 2 above, if shimmings are not provided, will the conditions cause over-stress on the supports or piping systems? -
- 4. In conjunction with 3 above, if extensive potentially over-stress condi- .
tions did exist without proper structural shimming having been performed, 1 would it be a 10 CFR 50.55(e) reportable item that had never been reported?
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l SSER for License Condition 2.C.(11), item 4 .
PG&E shall identify all pipe supports for which themal. g6ps have 'been specifically included in the piping thermal analyses. For there cases the _i licen's ee shall develop a program for periodic inservice inspect-icn to assure that these gaps are maintained throughout the operating life of the plant.
PGSE shall submit to the NRC staff a report containing the gap monitoring program.
Comments _
The licensee measures taken and proposed future actions are considered to be ,
acceptable.
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S$6R.for 1.icense Cor.dition 2.C.(ll), Item 5 PG&E shall provide to the hRC the procedures and schedules for :.he hot walkdowns of the main steam system piping. PG&E shall document the main steam hot walkdown results in e reocrt to the !!RC Staff.
Ccmments
- 1. The objective failed to describe inspection cf spacings provided for piping compcnent seismic (DE, DDE, and Mosgrf) movements at operating (hot) positions. The program did not provide neasures to inspect for:
(1) piping components that nay doma electricalpanelshndcabletrays,fepotentiall'nterferencessuchas2)c6mponents.thatm by closely spaced structures, and (3) interference th-+. could change the p9 ping ratural frequencies thus caused redistributi.on f support loads, or shif ting cf bia' nce loadings to the r. ore criticil .es tpment nozzle connections.
- 2. Fricticn.of the s)iding type support.wes observed by th. .lidensee to be a ,
problem in meetiog the Code, and, it wa.s ~ replaced by a sway strut. It.can reasonably be assen,ed that ccetain type's of sliding s.upports installed at Diable Canyon ccald causs exce:sive frictional force. Did PRP inquire into the licer.see measure to review the issue en a generic basis?
- 3. There appears to be a larx of en orderly and systematic presentation on the PRP performance of their, assignmer.t at the site. Please provide the following technical information:
- a. Temcerature sersus mecsurement 'inatrix of all data points.
- b. P& yds, piping isometrf ts. support details, and pertinent structura) drawings and skettbes.
- c. Record of pretest walldownt including review of maximum thermal plus seis.nic movements, and jespection of possible locaticrs that -
cculd be in violation of the above review data conclusions. .
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SSER for Licente Condition 2.C.(11), Item 6 PG&E sha'il conduct a review of the ' Pipe Support Design Tolerance Clarifica-tion" (PSDTC) Program and the "D$ablo Problem" (DP) System activities. The review shall include specific identification of the following:
- 1. Support changes which deviated from the defined PSDTC Program scope
- 2. Any significant deviations between as-built and design configurations stencing from the PSDTC or OP activities ,
- 3. Any unresolved matters idertified by the DP system ,
The purpcse of this review is to ensure that.all design changes and modifica-tions have been resolved and documented in an appropriate manner. Upon completion, PG&E shall submit a report to the 11RC staff documenting the results of this review, Comments ,
- 1. PDSTC
- a. Approximately 15,000 TCs were written since the inception of the program. This means that about 70% of all the large bore and small bore support design including calculations had been "quickly fixed (or more appropriately - deviated)" by few site engineers. It was inconceivable tnat the licensee management was unaware of a 0A program breakdown of this magnitude. .Did PRP investigate whether or -
not there had been any DCP management's predetermined decision to bypass QA program commitments relative to design change control (FSAR commits to 10 CFR 50 Appendix B QA criteria)?
- b. The SSER stated that, "Upon completion of construction of the support, the complete as-built package, including any PSDTC forms associated with that support, was forwarded by Construction to ,
Engineering for final acceptance in accordance with project engineering procedures." The PRP conclusion was contrary to the evidence provided by an anonymous alleger during the staff interview ccnducted on May 22, 1984. The documentational evidence showed that some of the TCs were not included in the as-built packages. These TC items included abandoned concrete expansion anchor bolt drilled holes, and added on wing plates to the original base plates.
- c. Many rather significant engineering concerns were brought forth during the May 22, 1984 meeting with the anonymous alleger. The trEnscript was still in confidential status. The staff stated in J the transcript that due to the lateness of tre day, a followup on the meeting could probably be scheduled in two weeks. The SSER j should address specific reasons for which the followup meeting was i not Scheduled. j 4
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- d. Four of the scpport installations were examined by the PRP team,,
the team consisted of one NRR Branch chief, one consultant from Battelle, and two consultants fr0m EG&G Jdaho, fly concerns are:
(1) the sample si:e selected for Consideringappeared observation the sizetoofbethe group,ly small judging by thra NRC unusual ,
regional inspection standard.
(2) Have any or all of the team members had any prior hands :ce hardware inspection experience?
t J (3) Please provide sufficient detail descriptions on how the ,
supports were inspected, and what attributes have been checked -
and verified.
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The licensee measures taken, and the PRP review and evaluation effort are considered to be acceptable.
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S5ER for License Corditfon E.c.(11), Ite.n 7 ,
DGAL sfiell conduct a program to' demonstrate f.het the Pclim:ing tecnnical topict have been tidequately addressed in the design of cmall and large bere piping supports:
(a) 'inclusi.or of werping normal and shear stresses due to torsfon f n those 1 open sedtions where yarping effects are significa G.
(b) Fesblution of differences betweet, the AISC Cod,e and Becht;l criteria with regard to allowable lengt.hs of unbeaced angle sectient in fending.
h) Consi6eration of 'iteraf/torsibnal buckling under axiaI lodding of Sngle ineabert.
(d) Irclusion of axial and torsional loads due to soad 2.'ccentricity where appropriate.
(e) Correct cticulatleo of pipe support fur.damental frequgrey by Rayleigh's
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method.
(f) Consideration of ficre bevel weld effective throat thickness as used on struct~ure,1 steel tubing with an outside radius of loss than 2T.
PS6E shall submit a report to the NRC Staff documenting the results of the prograra.
Cearnen ts Above allegation items were not astigned to me for followup ections.
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