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Category:NRC TECHNICAL REPORT
MONTHYEARML20058P5181990-05-11011 May 1990 Accident Sequence Precursor Program Event Analysis 323/87-005 R2, Loss of RHR Cooling Results in Reactor Vessel Bulk Boiling ML20058P5131990-04-0505 April 1990 Accident Sequence Precursor Program Event Analysis 424/PNO-IIT-90-02A, Loop,Diesel Generator Failure & 36 Min Interruption of SDC During Mid-Loop Operation ML20058P5221990-02-0303 February 1990 Accident Sequence Precursor Program Event Analysis Loss of Reactor Protection Sys Bus B Causes Loss of Shutdown Cooling ML20248F0001989-09-29029 September 1989 Debris in Containment Recirculation Sumps, Technical Review Rept ML20246C9671988-11-22022 November 1988 Initial OL Review Rept,Suppl 1 for Seabrook Station Unit 1 ML20204J6141988-08-31031 August 1988 AEOD/E807, Pump Damage Due to Low Flow Cavitation ML20245B6061988-08-31031 August 1988 Inadequate NPSH in HPSI Sys in Pwrs, Engineering Evaluation Rept ML20196G5251988-06-15015 June 1988 Technical Review Rept T809, Blocked Thimble Tubes/Stuck Incore Detector ML20245H9601988-04-15015 April 1988 BWR Overfill Events Resulting in Steam Line Flooding, AEOD Engineering Evaluation Rept ML20148D0671988-03-17017 March 1988 Headquarters Daily Rept for 880317 ML20148B3291988-03-14014 March 1988 Headquarters Daily Rept for 880314 ML20196H6351988-03-0808 March 1988 Headquarters Daily Rept for 880308 ML20196G8881988-03-0303 March 1988 Headquarters Daily Rept for 880303 ML20147E3961988-01-0606 January 1988 Rept of Interview W/Rg Lagrange on 841206 & 14 to Discuss Info Contained in B Hayes 841017 Memo Identifying Series of Submittals Received from Util Between 1980 & 1984 ML20147E3211988-01-0606 January 1988 Rept of Interview W/Rg Lagrange to Discuss Gpu 830520 & s Re Environ Qualification equipment.Marked-up 850409 Statement from H Hukill Also Encl ML20237L3001987-08-24024 August 1987 AEOD/E709 Engineering Evaluation Rept Re Auxiliary Feedwater Trips Caused by Low Suction Pressure.Draft Info Notice Encl ML20234B4681987-06-30030 June 1987 Loss of Residual Heat Removal System.Diablo Canyon Unit 2, April 10,1987 ML20235C9311987-06-23023 June 1987 Rept to ACRS Re Humboldt Bay Unit 3 - Core II ML20245B5101987-03-27027 March 1987 Pressurizer Code Safety Valve Reliability ML20212F6581986-12-31031 December 1986 Technical Review Rept, Degradation of Safety Sys Due to Component Misalignment &/Or Mispositioned Control/Selector Switches ML20212D9091986-12-23023 December 1986 Localized Rod Cluster Control Assembly (Rcca) Wear at PWR Plants, Engineering Evaluation Rept ML20212B0321986-12-17017 December 1986 Emergency Diesel Generator Component Failures Due to Vibration, Engineering Evaluation Rept ML20214R4851986-10-0909 October 1986 Initial OL Review Rept for Seabrook Station Unit 1 ML20212K6641986-08-0707 August 1986 Inadvertent Recirculation Actuation Signals at C-E Plants, Technical Review Rept ML20211P5531986-03-25025 March 1986 Rept to Commission:Review of Allegations Mgt for Diablo Canyon ML20206H0871986-03-0303 March 1986 Allegation Review Data Sheet for Case 4-85-A-013 Re Const Activities.Addl Info Requested from Alleger.Case Closed Due to Lack of Response.Related Info Encl ML20206H0761986-01-21021 January 1986 Allegation Review Data Sheet for Case 4-84-A-085 Re Alteration of Personnel Records.Based on Resolution of Allegation 4-84-A-094,case Closed ML20137X6151986-01-0909 January 1986 Engineering Evaluation of Deficient Operator Actions Following Dual Function Valve Failures ML20234F4751985-12-17017 December 1985 Licensing of Power Reactors by Aec ML20234F5601985-12-17017 December 1985 Draft Hazards Analysis ML20214T2211985-11-25025 November 1985 Initial OL Review Rept:Millstone Point Unit 3 ML20211P6301985-10-21021 October 1985 Partially Withheld Diablo Canyon - Allegations of Misconduct by NRC Employees, Rept of Investigation ML20206H0371985-10-0202 October 1985 Allegation Review Data Sheet for Case 4-85-A-044 Re Lack of Effective QA Programs & QC Insps.Based on Insp Rept 50-482/85-22,allegation Closed ML20137B1231985-09-16016 September 1985 HPCS Sys Relief Valve Failures, Engineering Evaluation Rept ML20206G8431985-09-0303 September 1985 Allegation Review Data Sheet for Case 4-84-A-013 Re Improper Termination of Employee Due to Refusal to Weld Laminated Pipe.Welding non-safety Related.Case Closed on 850827.W/ 840315 Telcon Record & Addl Info ML20206G8051985-08-27027 August 1985 Allegation Review Data Sheet for Case 4-84-A-114 Re Drugs Planted at Plant.Evidence Destroyed in Testing.Based on Insp Rept 50-482/85-03 & Mullikin 850429 Memo,Case Closed IR 05000482/19850101985-08-27027 August 1985 Allegation Review Data Sheet for Case 4-84-A-195 Re Quality First.Fuel Load Issue Resolved in Insp Rept 50-482/85-10. Technical Issues to Be Resolved Prior to Full Power Licensing.Case Closed w/850815 Memo to File ML20209G3051985-08-0909 August 1985 Closure of ECCS Min Flow Valves, Engineering Evaluation Rept.Recommends IE Issue Info Notice to Remind Licensees of Importance of Min Flow Bypass Capability as Essential Pump Protection Feature ML20206H0801985-07-30030 July 1985 Allegation Review Data Sheet for Case 4-84-A-007 Re Intimidation of QC Inspector.Forwards Documents Closing Allegation.W/O Encls IR 05000482/19840121985-07-30030 July 1985 Allegation Review Data Sheet for Case 4-84-A-008 Re Improper Const Practices.Insp Rept 50-482/84-12 Issued on 841012 & Closeout Ltr Sent on 850405 ML20147E4401985-06-20020 June 1985 Rept of Interview W/Cw Smyth on 850510.Smyth Advised of Unfamiliarity W/Environ Qualification Program in Technical Sense & W/Documentation Needed to Qualify Individual components.Marked-up Lw Harding Statement Encl ML20199G0701985-05-0303 May 1985 Partially Withheld Statement of Decision Re Allegation AQ-38 Concerning Alleged Harassment of QC Inspectors Upon Observation of Weld Defects on vendor-inspected Restraints. Allegation Substantiated.Addl Allegation Repts Encl ML20147H0101985-04-16016 April 1985 Draft Summary Rept for Regional Evaluation of Texas Utils Electric Co,Comanche Peak Steam Electric Station ML20206G9151985-03-12012 March 1985 Allegation Review Data Sheet for Case 4-84-A-015 Re Harassment of Mechanical/Welding QC Inspector for Writing Nonconformance Rept Re Improper Welding Amperage by Superintendent.Util Rept Issued & Case Closed ML20147G9901985-01-31031 January 1985 Summary Rept for Regional Evaluation of Texas Utils Electric Co,Comanche Peak Steam Electric Station ML20205Q7691985-01-18018 January 1985 Status Rept Mechanical/Piping Area. Related Info Encl ML20209E0581985-01-15015 January 1985 Supplemental Summary Rept for Regional Evaluation ML20206G8861985-01-0909 January 1985 Allegation Review Data Sheet for Case 4-85-A-004 Re Electrical Installations.Insp Required.Related Info Encl ML20214R5681984-12-31031 December 1984 Shoreham Nuclear Power Station Initial OL Readiness Assessment ML20214T7251984-11-30030 November 1984 Summary Rept for Regional Evaluation of Diablo Canyon Unit 2 1990-05-11
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211A9981999-07-12012 July 1999 Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure ML20207A7181999-05-13013 May 1999 Safety Evaluation Supporting Amends 134 & 132 to Licenses DPR-80 & DPR-82,respectively ML20206H2861999-05-0303 May 1999 Safety Evaluation Supporting Amends 133 & 131 to Licenses DPR-80 & DPR-82,respectively ML20206D5661999-04-29029 April 1999 Safety Evaluation Supporting Amends 132 & 130 to Licenses DPR-80 & DPR-82,respectively ML20205B6061999-03-26026 March 1999 Safety Evaluation Supporting Amends 131 & 129 to Licenses DPR-80 & DPR-82,respectively DCL-99-045, 1998 Annual Financial Rept for PG&E Corp. with1998-12-31031 December 1998 1998 Annual Financial Rept for PG&E Corp. with ML20249B6881998-06-11011 June 1998 Safety Evaluation Supporting Amends 128 & 126 to Licenses DPR-80 & DPR-82,respectively ML20249B5961998-06-0505 June 1998 Safety Evaluation Supporting Amends 127 & 125 to Licenses DPR-80 & 82,respectively ML20249B6041998-06-0505 June 1998 Safety Evaluation Supporting Amends 126 & 124 to Licenses DPR-80 & DPR-82,respectively ML20248D4041998-05-28028 May 1998 Safety Evaluation Supporting Amends 125 & 123 to Licenses DPR-80 & DPR-82,respectively ML20248L8761998-03-12012 March 1998 Safety Evaluation Supporting Amends 124 & 122 to Licenses DPR-80 & DPR-82,respectively ML20197B7091998-02-27027 February 1998 Safety Evaluation Supporting Amends 123 & 121 to Licenses DPR-80 & DPR-82,respectively ML20203J5141998-02-26026 February 1998 LER 98-S02-00:on 980127,following Security Sys Failure Compensatory Measures Were Not Implemented within 10 Minutes Due to Personnel Error.Caused by Failed Disk Drive. Replaced Disk Drives,Reviewed Security Computer Maint Plans ML20203L4881998-02-17017 February 1998 Safety Evaluation Supporting Amends 122 & 120 to Licenses DPR-80 & DPR-82,respectively ML20203L2981998-02-13013 February 1998 Safety Evaluation Supporting Amends 121 & 119 to Licenses DPR-80 & DPR-82,respectively ML20203M4321998-02-0303 February 1998 Safety Evaluation Supporting Amends 120 & 118 to Licenses DPR-80 & DPR-82,respectively ML20217G5151997-12-31031 December 1997 1997 PG&E Corp Annual Rept ML20205F5881997-07-24024 July 1997 Decommissioning Cost Estimate for Diablo Canyon Power Plant,Units 1 & 2 ML20149H4281997-07-17017 July 1997 Corrected SE Re Amends 119 & 117 to Licenses DPR-80 & DPR-82,respectively ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML18102B6911997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Diablo Canyon Power Plant,Units 1 & 2.W/970218 Ltr ML17083C6231997-01-31031 January 1997 Rev 4 to WCAP-13705, W Setpoint Methodology for Protection Sys Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML16343A4741997-01-31031 January 1997 WCAP-11595,Rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology Diablo Canyon Units 1 & 2 24 Month Fuel Cycle Evaluation. ML16342D5351997-01-31031 January 1997 WCAP-14826, Instrumentation Calibr & Drift Evaluation Process for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML16342D5541996-12-31031 December 1996 Non-proprietary Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. DCL-97-045, Pacific Gas & Electric Co 1996 Annual Rept1996-12-31031 December 1996 Pacific Gas & Electric Co 1996 Annual Rept ML20129G7771996-10-25025 October 1996 Safety Evaluation Supporting Amends 116 & 114 to Licenses DPR-80 & DPR-82,respectively ML20129G9351996-10-25025 October 1996 Safety Evaluation Supporting Amends 117 & 115 to Licenses DPR-80 & DPR-82,respectively ML20129J4311996-10-18018 October 1996 Safety Evaluation Approving Corporate Restructuring & Establishment of Holding Company Under Temporary Name PG&E Parent Co.,Inc of Which PG&E Would Become Wholly Owned Subsidiary ML20117E5541996-08-19019 August 1996 Safety Evaluation Supporting Amends 115 & 113 to Licenses DPR-80 & DPR-82,respectively ML20116B8491996-07-22022 July 1996 Revised Special Rept SR 95-03:on 950621,EDG 1-2 Failed to Load During Surveillance Testing.Caused by Loose Fuse Holder Contact Clip.Retensioned Loose Fuse Holder Contact Clip & Tightened Loose Wire Connection ML20116B8521996-07-22022 July 1996 Revised Special Rept SR 95-04:on 950718,EDG 1-2 Load Swings Occurred.Caused by Defective Electronic Governor Stability Potentiometer.Replaced Electronic Governor DCL-96-155, Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor1996-07-22022 July 1996 Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor ML20117K4671996-05-28028 May 1996 Safety Evaluation Supporting Amends 113 & 111 to Licenses DPR-80 & DPR-82,respectively ML20236Q2611996-04-15015 April 1996 Rev 0 to DCP M-050284, Design Change Package for Installation of CCW Surge Tank Pressurization Sys for Unit 1 ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML20092F3411995-08-23023 August 1995 Corrected SE Supporting Amends 107 & 106 to Licenses DPR-82 & DPR-80,respectively ML18064A8631995-08-14014 August 1995 LER 95-004-00:on 950714,determined That Redundant DG Circuits Not Separated Per App R Due to Insufficient App R Program Documentation.Hourly Fire Tour Established in EDG 1-1 Room & Review of LERs for App R Completed ML20082H9121995-04-11011 April 1995 Safety Evaluation Supporting Amends 99 & 98 to Licenses DPR-80 & DPR-82,respectively ML18100B2981994-05-24024 May 1994 LER 94-014-00:on 940426,SG 1-2 Automatically Started When Two Indicating Light Sockets Shorted Together Due to Personnel Error.Description of Event & Lessons Learned Will Be Published in Operations Incident Summary.W/940524 Ltr ML20063M1481994-03-0303 March 1994 Safety Evaluation Supporting Amends 90 & 89 to Licenses DPR-80 & DPR-82,respectively ML20063M1111994-03-0202 March 1994 Safety Evaluation Supporting Amends 89 & 88 to Licenses DPR-80 & DPR-82,respectively ML20063M0431994-02-24024 February 1994 Safety Evaluation Supporting Amends 88 & 87 to Licenses DPR-80 & DPR-82,respectively ML16342C3091993-12-31031 December 1993 Monthly Operating Repts for Dec 1993 for Dcnpp Units 1 & 2 ML16342A3691993-08-31031 August 1993 Revised MOR for Aug 1993 for Dcnpp Unit 1 ML16342A3681993-07-31031 July 1993 Revised MOR for July 1993 for Dcnpp Unit 1 ML20046A6611993-07-21021 July 1993 Cycle 6 Startup Rept. ML20059G6811993-06-30030 June 1993 Revised MOR for June 1993 for Dcnpp Unit 1 ML16342A3671993-05-31031 May 1993 Revised MOR for May 1993 for Dcnpp Unit 1 ML20045D1731993-05-31031 May 1993 Monthly Operating Repts for May 1993 for Diablo Canyon,Units 1 & 2 1999-07-12
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Enclosure No. 2 NUCLEAR REGULATORY C0tHISSION STRUCTURAL ENGINEERING BRANCH BRANCH POSITION ON THE SEISMIC DESIGN OF DIABLO CANYON 1.
The applicant will be asked to specify a magnitude 7.5 earthquake at the HOSGRI fault with horizontal spectra normalized to 0.75g Regulatory Guide 1.60 spectral shapes may be used. Use of the HOSGRI spectral shape will require further justification since it is believed that the HOSGRI spectral' shape was developed for lower magnitude earthquakes.
2.
A reduction in both horizontal and vertical response spectra will be permitted depending on the actual equivalent length of individual IFieW buildings. This reduction recognizes that ground motions are not synchronized under structures during earthquakes.
In other words, different points in the foundation base slab will not experience, the maximum free field ground potion,at the same time. The quiv-alent length of each individual structure will be equal to the square root of the building base slab area. The magnitude of the reduction factor shall be determined as the average of the value from the theoretical procedure given by Scanlan (see Reference) for a harmonic wave and the value determined using trie Pacoima Dam record obtained in the 1971 San Fernando earthquake. The harmonic wave in the Scanlan procedure will be assumed to have a frequency of 7 hertz.
3.
Where such reduction in response spectra is used, the applicant will be asked to appropriately account for additional tilting and torsion which may result from the nonsynchronized earthquake motions considered in item 2, above.
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4.
In reevaluating the capability of the plant structure, systems and components, inelastic behavior may be relied upon to absorb the ground motion energy. Where such a behavior is relied upon, a ductility ratio not exceeding 1.2 may be used in determining seismic loads and motions. Foreachparticul5rstructurewhere this ductility is relied upon, the applicant. will be asked to provide justification and bases for assuring that the increased strains and deformations will not affect the safety functions of the plant systems and structures. Th'is ductility ratio is permitted by the SEB staff for near-field earthquakes, such as those associated with the HOSGRI fault, which tend to have shorter duration.s of strong motion.
It is recognized that for short duration earthquakes, the use of elastic response spectra tends to produce overly conservative results.
5.
It was also decided that the a,nalytical work required to develop individual response spectra fo'r the various plant buildings will be performed by the applicant and a report will be requested thereafter. The SEB staff and Dr. Newmark will review this report and only thereafter will finalize the SER for release.
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Isa S. Sihweil, Chief Structural Engineering Branch Division of Systems Safety
Reference:
"Seisnic Nwe Effects on Soil Structure Interaction" by R. H.
Scanlon, 3rd 9fIRT Conference,1975