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Category:Report
MONTHYEARML22119A0922022-05-0303 May 2022 Ril 2022-07, Assessment of San Onofre Concrete Susceptibility Against Irradiation Damage ML21280A1032021-12-0606 December 2021 Updated Biological Assessment of Impacts to Federally Listed Species Under NMFS Jurisdiction for SONGS Decommissioning ML21242A0592021-09-30030 September 2021 Biological Assessment of Impacts to Federally Listed Species Under NMFS Jurisdiction for SONGS Decommissioning ML21270A2172021-09-27027 September 2021 LTR-21-0264 David Lochbaum, Union of Concerned Scientists, Letter Study Regarding Spent Fuel in Dry Storage at San Onofre Nuclear Generating Station ML21165A0822021-06-0303 June 2021 the Independent Spent Fuel Storage Installation, Facility Change Report, Summary Report of Commitment Changes ML20178A3632020-06-22022 June 2020 Defueled Safety Analysis Report ML20118D0742020-04-27027 April 2020 SONGS Spotlight Section FAQ Updated 3-31-2020 ML20113E9332020-04-22022 April 2020 SONGS CEP-SCE Joint Response to NEIMA 108 Questionnaire ML20034D9542020-02-0303 February 2020 Salvage 6-10 - Health Physics Sample Records ML20029D1642020-01-23023 January 2020 Additional Protocol No Changes Report for Reporting Year 2019 San Onofre Nuclear Generating Station (SONGS) Unit 2 ML19158A0922019-06-0404 June 2019 Facility Change Report, Summary Report of Commitment Changes, and Cycle Specific Technical Specification Bases Page Updates San Onofre Nuclear Generating Station (SONGS) Units 1, 2, 3, and the Independent Spent Fuel Storage Installation ML19011A4572019-01-11011 January 2019 ISFSI Pad Surveys at San Onofre Nuclear Generating Station Final ML18330A0032018-11-16016 November 2018 Southern California Edison Company; San Onofre Nuclear Generating Station; Non-proprietary Summary of the Holtec Proprietary MPC-37 Drop Analysis in Holtec Report Number HI-2188261 Rev. 3, November 16, 2018 ML18331A0192018-10-18018 October 2018 Southern California Edison Company; San Onofre Nuclear Generating Station; Summary of the Root Cause and Apparent Cause Evaluations of August 2018 Download Event at SONGS ML18176A0352018-06-21021 June 2018 Defueled Safety Analysis Report ML18233A4692018-06-18018 June 2018 Comment Disposition for High Energy Arcing Faults (Heafs) in Electrical Equipment Phase 2 ML17037D1152017-02-0404 February 2017 SONGS ISFSI Only PSP Amendment Nshcd Pages ML20034E4702016-11-15015 November 2016 SCE Ltr to Don Transmitting RSCS Risk Analysis for Mesa Land ML16176A3392016-10-28028 October 2016 Decommissioning Lessons Learned Report and Transmittal Memorandum ML16190A4032016-06-27027 June 2016 Transmittal of Defueled Safety Analysis Report ML16181A3352016-06-27027 June 2016 Defueled Safety Analysis Report ML20034E4672016-05-19019 May 2016 Mesa Bounding Dose Evaluation Final Signed ML16111A0032016-04-25025 April 2016 Completion of Action Nos. 1a, 1b, and 2 Associated with Topic 1 of the San Onofre Steam Generator Tube Degradation Event Lessons Learned ML15159A1882015-06-0404 June 2015 Independent Spent Fuel Storage Installation (Isfsi), Submittal of Summary Report of Commitment Changes, and Cycle Specific Technical Specification Bases Page Updates ML15015A4192015-03-0606 March 2015 Review of Lessons Learned from the San Onofre Steam Generator Tube Degradation Event ML15071A0202015-03-0303 March 2015 Enclosure 2, Current SONGS Synchronous Condenser Contamination Prevention Monitoring Program, RSCS Technical Support Document No. 14-140, Revision 0 ML15071A0192015-03-0303 March 2015 Enclosure 1, Current SONGS Switchyard Area Synchronous Condenser Footprint Proposed Characterization for Final Status Survey, Technical Data Record Document No. 12-9234618-001 ML15014A1202015-01-14014 January 2015 Feedback for Specific Public Meetings ML15014A0942015-01-14014 January 2015 SONGS Communications External Survey Results ML19311C7282014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 28 ML19311C7402014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 40 ML19311C7182014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 18 ML19311C7392014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 39 ML19311C7202014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 20 ML19311C7382014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 38 ML19311C7102014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 10 ML19311C7112014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 11 ML19311C7322014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 32 ML19311C7042014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 5 ML19311C7032014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 4 ML19311C7052014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 6 ML19311C7062014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 7 ML19311C7072014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 8 ML19311C7262014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 26 ML19311C7362014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 36 ML19311C7252014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 25 ML19311C7132014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 13 ML19311C7142014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 14 ML19311C7302014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 30 ML19311C7212014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 21 2022-05-03
[Table view] Category:Technical
MONTHYEARML22119A0922022-05-0303 May 2022 Ril 2022-07, Assessment of San Onofre Concrete Susceptibility Against Irradiation Damage ML21280A1032021-12-0606 December 2021 Updated Biological Assessment of Impacts to Federally Listed Species Under NMFS Jurisdiction for SONGS Decommissioning ML21270A2172021-09-27027 September 2021 LTR-21-0264 David Lochbaum, Union of Concerned Scientists, Letter Study Regarding Spent Fuel in Dry Storage at San Onofre Nuclear Generating Station ML20178A3632020-06-22022 June 2020 Defueled Safety Analysis Report ML19158A0922019-06-0404 June 2019 Facility Change Report, Summary Report of Commitment Changes, and Cycle Specific Technical Specification Bases Page Updates San Onofre Nuclear Generating Station (SONGS) Units 1, 2, 3, and the Independent Spent Fuel Storage Installation ML19011A4572019-01-11011 January 2019 ISFSI Pad Surveys at San Onofre Nuclear Generating Station Final ML18330A0032018-11-16016 November 2018 Southern California Edison Company; San Onofre Nuclear Generating Station; Non-proprietary Summary of the Holtec Proprietary MPC-37 Drop Analysis in Holtec Report Number HI-2188261 Rev. 3, November 16, 2018 ML18176A0352018-06-21021 June 2018 Defueled Safety Analysis Report ML18233A4692018-06-18018 June 2018 Comment Disposition for High Energy Arcing Faults (Heafs) in Electrical Equipment Phase 2 ML17037D1152017-02-0404 February 2017 SONGS ISFSI Only PSP Amendment Nshcd Pages ML20034E4702016-11-15015 November 2016 SCE Ltr to Don Transmitting RSCS Risk Analysis for Mesa Land ML16190A4032016-06-27027 June 2016 Transmittal of Defueled Safety Analysis Report ML20034E4672016-05-19019 May 2016 Mesa Bounding Dose Evaluation Final Signed ML15071A0202015-03-0303 March 2015 Enclosure 2, Current SONGS Synchronous Condenser Contamination Prevention Monitoring Program, RSCS Technical Support Document No. 14-140, Revision 0 ML15071A0192015-03-0303 March 2015 Enclosure 1, Current SONGS Switchyard Area Synchronous Condenser Footprint Proposed Characterization for Final Status Survey, Technical Data Record Document No. 12-9234618-001 ML19311C7312014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 31 ML19311C7302014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 30 ML19311C7182014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 18 ML19311C7392014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 39 ML19311C7402014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 40 ML19311C7352014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 35 ML19311C7362014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 36 ML19311C7372014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 37 ML19311C7332014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 33 ML19311C7242014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 24 ML19311C7292014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 29 ML19311C7322014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 32 ML19311C7342014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 34 ML19311C7382014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 38 ML19311C7262014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 26 ML19311C7282014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 28 ML19311C7232014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 23 ML19311C7202014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 20 ML19311C7212014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 21 ML19311C7082014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 9 ML19311C7102014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 10 ML19311C7052014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 6 ML19311C7042014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 5 ML19311C7062014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 7 ML19311C7072014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 8 ML19311C7022014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 3 ML19311C7032014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 4 ML19311C7002014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 1 ML19311C7012014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 2 ML19311C7112014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 11 ML19311C7132014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 13 ML19311C7222014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 22 ML19311C7272014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 27 ML19311C7162014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 16 ML19311C7142014-09-23023 September 2014 Public Watchdogs - NRC 2.206 Petition Exhibits 1-38, Part 14 2022-05-03
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AMENDED FINAL REPORT REGARDING PIPE SUPPORT DESIGN DEFICIENCIES San Onofre Nuclear Generating Station Units 2 and 3 INTRODUCTION This report is submitted pursuant to 10CFR50.55(e)(3). It describes design deficiencies related to certain safety related pipe supports.
This report includes a description of the deficiencies, analysis of the safety implications and a summary of the corrective action taken.
BACKGROUND By letter dated July 6, 1979, Edison submitted a final report related to a lack of documented design calculations for certain safety related pipe supports. This report amends that report to include six additional deficiencies relating to safety related pipe support design activities.
These deficiencies were reviewed in a meeting with the NRC resident inspector on January 31, 1980 and are considered reportable in accord-,
ance with 10CFR50.55(e).
DESCRIPTION OF DEFICIENCY
- 1. Insufficient Pipe Bearing Surface A maximum of 500 large pipe supports for thin wall piping may not meet design requirements for pipe bearing surface. In these cases, loading conditions could result in local pipe stress allowables being exceeded. The problem was discovered in mid 1977. Design practices and criteria prior to this date did not provide for specific evaluation of local stresses.
- 2. Frictional Loading on Pipe Support Framing The effect of loads imposed by thermal expansion movement of piping on pipe support framing may not have adequately considered in the design of certain 8 inch and larger pipe supports. The number of supports affected is included in (1) above. The problem is that the structural load resulting from the thermal expansion of the pipe would cause additional loading on the pipe support structure.
The problem was discovered in late 1977 and was most probably attributable to a lack of written design criteria and formal civil structural design calculations to support design verification activities.
0 0 AMENDED FINAL REPORT REGARDING PIPE Page Two SUPPORT DESIGN DEFICIENCIES SAN ONOFRE UNITS 2&3
- 3. Lack of Reinforced Branch Connections Eight-six ASME thin wall pipe spools provided to Bechtel by Pullman Power Products required detailed design calculations to determine the adequacy of the fabricated spools to meet design requirements.
The spools in question were fabricated using non-reinforced branch connections. This condition resulted from the material specifica tion allowing the vendor to utilize either a tee or a branch connec tion while the original Bechtel stress analysis was based on piping isometric drawings which indicated tee connections.
- 4. Use of Dissimilar Metal Attachments Carbon steel integral attachment material had been used on stainless steel lines with design temperatures between 150 F and 300 F. In certain configurations (about 100 pipe supports) the use of carbon steel may result in over stressing the welds between the attachment and pipe. The problem was discovered when it was determined that dissimilar metal attachments were being supplied based on material substitutions allowed by the piping material specifications.
- 5. Embed Plate Stiffness Supports attached to base plates may have been designed without adequate consideration of plate stiffness. Additionally, certain plate designs may not have adequately considered biaxial bending.
These problems may affect 500 pipe supports. This problem was discovered in late 1978 and was attributed to lack of formal design criteria and documented civil/structural calculations. A maximum of 500 hangers were affected by this problem.
- 6. Use of Structural Tees Instead of Dummy Stubs Under certain loading conditions, the specified structural tees may have insufficient lateral strength. Additionally, the local stress at the pipe tee interface may exceed local stress allowables.
Dummy stubs should have been specified. This problem may affect 50 pipe supports.
Analysis of Safety Implications While no specific safety analysis has been conducted, a generic review of the deficiencies described above and those addressed in our report of July 6, 1979 indicates that the design functions of certain individ ual .safety related pipe supports could have been affected if the defi ciencies had gone uncorrected. The corrective action measures described
AMENDED FINAL REPORT REGARDING PIPE Page Three SUPPORT DESIGN DEFICIENCIES SAN ONOFRE UNITS 2&3 in the following section of this report will assure that design defic iencies are corrected and that the pipe supports can perform their safety related functions.
CORRECTIVE ACTION In order to provide a systematic review of the six problems identified above, a startup system review program was initiated to review the total design of each piping system prior to turnover to startup. This program consists of a piping isometric drawing review, a pipe stress review (by checklist), a pipe support design review, pipe support walkdown inspec tion, and an analysis performed to support the design. All identified deficiencies are to be corrected prior to turning the system over for startup. Details of specific corrective actions applied to the individual problems are identified as follows:
- 1. Insufficient Pipe Bearing Surface Specific criteria was developed in 1978 to require evaluation of local bearing stresses and to specify acceptance criteria. This criteria was incorporated into the startup review program to assure that this problem is corrected. The addition of a wrapper plate or increased bearing surface is a typical physical modification required to resolve this problem.
- 2. Frictional Loading on Pipe Support Framing Design criteria has been developed to require evaluation of frac tional loading resulting from pipe thermal expansion in the design of the pipe support structure. This criteria was included in the startup review program to assure this problem is corrected. The addition of bracing is a typical physical modification required to resolve this problem.
- 3. Lack of Reinforced Branch Connections All cases have been analyzed and only four of the 86 cases required the addition of a collar to reinforce the existing branch connec tion. The addition of a reinforcing collar reduces the stress intensification factor to an acceptable value.
AMENDED FINAL REPORT REGARDING PIPE Page Four SUPPORT DESIGN DEFICIENCIES SAN ONOFRE UNITS 2&3
- 4. Use of Dissimilar Metal Attachments The specifications were revised to require stainless steel attach ments on stainless steel pipe. The startup system review program includes a check for proper attachment material consistent with the above criteria. The substitution of a stainless steel attachment for a carbon steel attachment is the physical modification required to resolve this problem if calculations cannot support the existing design.
- 5. Embed Plate Stiffness Design criteria has been developed to identify the procedure to be followed in the design of all base plates to incorporate plate flexibility and biaxial bending characteristics. This criteria is included in the startup review program to preclude recurrence of the problem. The physical modification required to resolve this problem consists of the addition of a brace or stiffening of the structural connection to the base plate.
- 6. Use of Structural Tees Instead of Dummy Stubs Specific design criteria has been developed to require evaluation of both the local stresses in the pipe and the lateral strength of the tee. This criteria is included in the startup review program to preclude recurrence of the problem. Substitution of a dummy stub for a structural tee or stiffening the existing structural tee is the required physical modification needed to resolve this problem.
Additional corrective actions taken by Bechtel to date beyond those dis cussed above include: the addition of several senior supervisors with strong civil structural background to the pipe support group; combining the pipe support and stress groups under one chief engineer; and revision of the project internal procedures governing the preparation, checking, review and approval of design calculations. Although all deficiencies have not been corrected to date, all deficiencies will be corrected prior to turning the system over for startup.