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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20211A9981999-07-12012 July 1999 Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure ML20205F5881997-07-24024 July 1997 Decommissioning Cost Estimate for Diablo Canyon Power Plant,Units 1 & 2 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 ML20086T1001991-12-31031 December 1991 Adequacy of Seismic Margins Assuming Increase in Amplitude of Diablo Canyon Seismic Long-Term Program Horizontal & Vertical Ground Motions Described in Sser 34 ML20246E4891989-06-30030 June 1989 Quarterly Sys Status Rept,2nd Quarter 1989,Sys 65 120V Instrument AC Sys,Sys 66 120V Security UPS Sys & Sys 67 125/250VDC Sys ML20153B0411988-03-31031 March 1988 Comments on ACRS Subcommittee on Diablo Canyon Meeting on 880223-24 in Burlingham,Ca Re Status of Long Term Seismic Program of Plant ML20155G0541984-04-30030 April 1984 Preliminary Rept on Status of IGSCC in SG Tube U-Bends ML20215H0121984-02-29029 February 1984 Followup of Alleged Deficiencies in QA Program at Diablo Canyon Nuclear Plant ML20210E7741984-01-25025 January 1984 Bostron-Bergen/Meddco Metals Allegations Investigation Interim Rept ML20072H3421983-12-31031 December 1983 Unit 1,Independent Design Verification Program Final Rept, Fifth Text Submittal ML20082T9221983-12-0909 December 1983 Semimonthly Rept 51:Diablo Canyon Verification Program ML20082G7021983-11-23023 November 1983 Semimonthly Status Rept 50,Diablo Canyon Verification Program ML20080K4131983-09-19019 September 1983 Rev 0 to Diablo Canyon Unit 1 Idvp Verification of Corrective Action,Turbine Bldg, Interim Technical Rept 56 ML20078B7111983-09-16016 September 1983 Rev 0 to Idvp Verification of Diablo Canyon Unit 1 Activities - Rupture Restraints, Interim Technical Rept 65 ML20080T0051983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Diablo Canyon Unit 1 Idvp - Small Bore Piping Rept ML20080T0031983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Diablo Canyon Unit 1 Idvp - Soil - Outdoor Water Storage Tanks ML20080T0131983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Idvp Valves ML20080T0091983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Diablo Canyon Unit 1 Idvp - HVAC Components ML20080T0161983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Idvp - HVAC Duct & Supports Rept ML20080S9981983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept Diablo Canyon Unit 1 Idvp - Soils - Intake Structure ML20080S9891983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Diablo Canyon Unit 1 Idvp - Verification Program for PG&E Corrective Action ML20080S9911983-09-0101 September 1983 Summary & Evaluation Rept of Rf Reedy Rept, Development of Svc-Related Contractor List for Nonseismic Design Work Performed for Diablo Canyon Nuclear Power Plant,Unit 1 Prior to 780601,Phase II ML20080S9941983-09-0101 September 1983 Summary & Evaluation Rept of Rl Cloud & Assoc Rept, Diablo Canyon Unit 1 Idvp - Verification of Design Analysis Hosgri Spectra ML20024D0831983-07-25025 July 1983 Rev 2 to Verification of Instrument & Control Design of Control Room Ventilation & Pressurization Sys, Interim Technical Rept 28 ML16341B9951983-07-25025 July 1983 Rev 2 to Verification of Pressure,Temp,Humidity & Submergence Environs Used for Safety-Related Equipment Spec Outside Containment for Auxiliary Feedwater Sys & Control Room Ventilation..., Interim Technical Rept 14 ML20077H9771983-07-0101 July 1983 Rept on Investigation of Reactor Coolant Pipe Weld Thickness at Diablo Canyon ML20076M0771983-06-15015 June 1983 Chronolgy of Events ML20065C2001983-02-18018 February 1983 Independent Design Verification Program,Electrical Equipment Analysis, Interim Technical Rept 33,Rev 0 ML20070S3911983-01-28028 January 1983 Verification Program, Semimonthly Rept 30 for 830111-24 ML20028D9581982-12-13013 December 1982 Verification of Fire Protection Provided for Auxiliary Feedwater Sys,Control Room Ventilation & Pressurization Sys, Safety-Related Portion of 4,160 Volt Electric Sys, Interim Technical Rept 18,Rev 0 ML20210P5751982-12-0707 December 1982 Interim Technical Rept on Diablo Canyon Unit 1 Idvp:Interim Technical Rept 12,Rev 0,Piping,Interim Technical Rept 17, Rev 0,Piping-Addl Samples ML20210P4821982-10-29029 October 1982 Rev 0 to Diablo Canyon Unit 1 Idvp Verification of Design Analysis Hosgri Spectra, Interim Technical Rept 10 ML20023A9351982-09-24024 September 1982 Independent Design Verification Program,Semimonthly Rept,IDVP-SM-Sept 1982 ML20210P2601982-09-13013 September 1982 Interim Technical Rept on Diablo Canyon Unit 1 Idvp,Small Bore Piping,Interim Technical Rept 30,Rev 0 ML20069D9461982-09-10010 September 1982 to Independent Design Verification Program Auxiliary Bldg, Interim Technical Rept ML20063J7261982-08-27027 August 1982 Semimonthly Rept 20,Diablo Canyon Verification Program, 820810-23 ML20210P1921982-06-22022 June 1982 Interim Technical Rept on Diablo Canyon Unit 1 Idvp, Verification of Design Analysis Hosgri Spectra - Interim Technical Rept 10,Rev 0 ML20053D3961982-05-28028 May 1982 Verification Program, Semimonthly Rept 14 ML20136B3361982-04-15015 April 1982 Comments on Rf Reedy,Inc,Qa Audit Rept on Safety-Related Activities Performed by PG&E Prior to June 1978 ML19264C7821982-02-27027 February 1982 Design Verification Program,Seismic Svc Related Contracts Prior to June 1978, Revision 1,Phase I ML16340C3591982-02-26026 February 1982 Progress Rept of Seismic Svc-Related Contracts Prior to June 1978, Project 105-4,Progress Rept 8 for Work Period 820213-26 ML20136B2781981-12-0303 December 1981 Design Verification Program Seismic Svc-Related Contracts Prior to June 1978 ML20204E9121981-11-26026 November 1981 Draft Seismic Verification Program ML16340C1211981-11-25025 November 1981 Semimonthly Status Rept Diablo Canyon Seismic Review Program,811112-23. ML20100M0471981-11-12012 November 1981 Draft Preliminary Rept of Project 105-4, Seismic Reverification Program ML20116B5501981-10-31031 October 1981 Draft Preliminary Rept on Design Interface Review of Seismic Reverification Program ML20039G2531981-08-31031 August 1981 Emergency Plan Evaluation Rept on Diablo Canyon Nuclear Power Plant,Pg&E Emergency Plan Dtd Aug 1981. ML16340B9981981-08-19019 August 1981 Evaluation Findings,Diablo Canyon Nuclear Power Plant Offsite Emergency Response Plans Exercise. ML20004B6851981-05-22022 May 1981 Scaling Laws for Large Earthquakes - Consequences for Physical Models. ML16340B7721981-05-22022 May 1981 Character of High Frequency Strong Ground Motion. 1999-07-12
[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 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 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 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 ML16342D5351997-01-31031 January 1997 WCAP-14826, Instrumentation Calibr & Drift Evaluation Process for 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. 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. DCL-97-045, Pacific Gas & Electric Co 1996 Annual Rept1996-12-31031 December 1996 Pacific Gas & Electric Co 1996 Annual Rept ML16342D5541996-12-31031 December 1996 Non-proprietary Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. 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 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 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 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 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 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 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 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20141M0471991-12-31031 December 1991 Pge Annual Rept - 1991 ML20086T1001991-12-31031 December 1991 Adequacy of Seismic Margins Assuming Increase in Amplitude of Diablo Canyon Seismic Long-Term Program Horizontal & Vertical Ground Motions Described in Sser 34 ML16341G4871991-11-30030 November 1991 Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Diablo Canyon Units 1 & 2 Nuclear Power Plants. ML20085D2951991-08-21021 August 1991 Field Exercise Scenario,Aug 1991 ML20070S7311990-12-31031 December 1990 Analysis of Capsule X from Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20065R8731990-11-30030 November 1990 Monthly Operating Repts for Diablo Canyon Units 1 & 2 for Nov 1990 ML20058P5181990-05-11011 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 ML20006E5441989-11-30030 November 1989 Review of Flow Peaking & Tube Fatique in Diablo Canyon Units 1 & 2 Steam Generators. ML20006C6681989-11-30030 November 1989 Nonproprietary WCAP-12416, Evaluation of Thermal Stratification for Diablo Canyon Units 1 & 2 Pressurizer Surge Line. ML20246E4891989-06-30030 June 1989 Quarterly Sys Status Rept,2nd Quarter 1989,Sys 65 120V Instrument AC Sys,Sys 66 120V Security UPS Sys & Sys 67 125/250VDC Sys ML20245G9881989-06-16016 June 1989 Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed DCL-89-117, Special Rept:On 890406,main Steam Line Radiation Monitor 1RM-71 Alarmed & Declared Inoperable.Caused by Failure of Detector Tube.Tube Replaced.Monitor Returned to Svc on 8904181989-04-27027 April 1989 Special Rept:On 890406,main Steam Line Radiation Monitor 1RM-71 Alarmed & Declared Inoperable.Caused by Failure of Detector Tube.Tube Replaced.Monitor Returned to Svc on 890418 ML20247M6281989-03-31031 March 1989 Nonproprietary Advanced Digital Feedwater Control Sys Median Signal Selector for Diablo Canyon Units 1 & 2 ML20246P4461989-03-23023 March 1989 Corrected Diablo Canyon Power Plant Unit 2 Second Refueling Outage Inservice Insp (ISI) Rept ML20236E0581988-12-31031 December 1988 Pacific Gas & Electric Co Annual Rept 1988 ML20247H0761988-11-30030 November 1988 Vol 1 to Bit Elimination Study for Diablo Canyon Units 1 & 2 ML20205S9071988-10-31031 October 1988 Steam Generator U-Bend Tube Fatigue Evaluation ML20153E5331988-08-29029 August 1988 Safety Evaluation Supporting Amends 31 & 30 to Licenses DPR-80 & DPR-82,respectively ML20206E7181988-05-30030 May 1988 Analysis of Capsule U from PG&E Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20195G3301988-04-30030 April 1988 Corrected Monthly Operating Repts for Apr 1988 for Diablo Canyon ML20153B0411988-03-31031 March 1988 Comments on ACRS Subcommittee on Diablo Canyon Meeting on 880223-24 in Burlingham,Ca Re Status of Long Term Seismic Program of Plant 1999-07-12
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, S.IMMARY AND EVALUATION REPORT Report
Title:
Diablo Canyon Unit 1 Independent Design Verification Program, HVAC Components' Report No. ITR-31, P 105-4-839-031, Revision 0 Report Date 1/14/83 Author Robert L. Cloud Associates Edward Denison Project Manager 8310180624 830901 PDR FOIA CALSOYA83-483 PDR
3 INTRODUCTION The Interim Technical Report 31( 'R-31) prepared by Robert L. Cloud and
. Associates (RLCA) for the Diablo Canyon' Nuclear Plant Independent Design Verification Program (DCNPP-IDVP) has been reviewed. -
ITR-31 summarizes the independent analysis and verification of a sample of heating, ventilating and air conaitioning (HVAC) components from DCNPP-1.
The sample consisted of the Volume damper 7A and the supply fan S-31, both located in the auxiliary building of DCNPP-1. The analysis and verificatinn showed both the volume dimper and supply fan to have sufficient structural integrity to withstand the effects of the postulated Hosgri earthquake.
However several generic concerra relating to Pacific Gas and Electric (PG&E) design analyses for HVAC components were noted and recomaendations for additional verifications to address these concerns were made.
SUMMARY
OF REPORT Volume damper 7A and supply fan S-51 were selected by RLCA as the initial' sample of DCNPP-1, HVAC components fer independent analysis and verification.
.e Volume damper 7A is located in the Unit 1 auxiliary building, at elevation 154 feet. The damper is a 24 inch diameter circular blade type.
The damper blade is operated by an electric motor actuator. Damper 7A is installed in a 24 inch diameter circular vertical duct in series with an identical Volume damper 7. The damper is attached to the duct by bolted .
flange connections. This run of duct is attached to sheet metal plenums, which are supported from the ceiling and floor siab.
Supply fan S-31 is located in the Unit 1 auxiliary building, at elevation 140 feet. The fan is an electric motor driven centrifugal fan. It draws air in through side inlets and expels air to the attached duct, which is attached to the fan by a flexible coupling. The fan is anchored to the floor slab.
The independent design verification of each . component consisted of
- 1. a field verification of the components' physical dimensions and configuration,
- 2. the developrent of a finite element mathematical model simulating the mass and stiffness characteris-tics of the component,
- 3. the determination of forces and moments for key areas -
of the component followed by stress detenninations 1 using standard engineering approaches,
- 4. - a comparison of computed stresses to stress allowables,
- 5. a comparison of the independent analysis to the PG&E design analysis.
Since no specific structural criteria relating to the HVAC components were addressed in the licensing documents, the following criteria were used.
Loading combinations were taken fr'am Chapter 5 of the Hosgri report.
Allowables for the Volume damper were determined using the ASME Boiler and Pressure Vessel (B&PV) code, Appendix XVII. Allowables for the supply fan
~
were determined using mechanical equipment criteria from the Hosgri report and material yield strength criteria fra ASME B and PV code yield strengths for component supports. Allowables for concrete expansion anchors were taken from the PG&E Engineering Standard for Ccncrete Expansion Anchors.
The finite element analysis of Volume damper 7A and attached ducting and supports showed the component to exhibit natural frequencies in the rigid range. Consequentially the equivalent static method, using the appropriate Hosgri floor response spectra zero period acceleration amplification factors, was used -to evaluate the forces and stresses in key locations. All stresses were found to be below allowables with the closest approach to the allowable being computed for a fillet weld on the damper actuator mounting plate (9346 psi vs.14,400 psi allowable).
The finite element analysis of supply fan S-31'showed the component to -
exhibit natural f,requencies below the rigid range. The computation of forces and stresses was therefore performed using'the response spectrum method. In
. . this ' analysis response _ spectra data corresponding to the component location and' 4% damping were 'taken from the Hosgri ' report. ~ The calculated stress were -
all below allowables, The closest approach to the allowable occurred for a frame member exhibiting a stress of 26885 psi vs. a 36,000 psi allowable.
_ Reviews of the PG&E design. analyses for both components were made with <
the intention to compare the design analysis results to the independent analysis results. However, the model usea in each design analysis differed so greatly from that used in the independent analysis as to preclude direct >
c ompa ri son. Instead a complete review of each design analysis was made to judge its adequacy.
The IDVP considered the methodology Osed in the design analysis of the Volume damper 7A to be acceptable because the system is rigid and conservative assumptions were made. The design analysis of the supply fan S-31 on the other hand, was found to be deficient. In the analysis unrealistic boundary conditions, inappropriate assumptions and incorrect data were used.
The IDVP issued five E01 reports for these two components. None of-these
! errors were of major significance since the verification analyses showed all stresses to be below allowble. The E01's have either been closed or classed error class C. The deficiencies found in the design analysis of the S-31 fan, however, were considered generic concerns. Because of these, the IDVP has .
recanmended that a review of the modeling of a sample of two types of fans and -
verification reviews of one of each type of HVAC component be undertaken.
EVALUATION The.ITR presents an adequate description of the procedures followed by RLCA in performing the independent analysis of the HVAC components. These procedures are acceptable and did uncover deficiencies in the PG8E design analyses for each couponent.
0 The ITR presents only a cursury description of the actual independent analyses. On the basis of the information provided no judgement of the technical adequacy of -these can be made. ' However audits of other RLC'A analysis docunents have indicated that the RLCA review and analysis procedures are both comprehensive and technically correct.
No specific structural criteria relating to HVAC components were addressed in the licensing docurents. RLCA developed structural criteria based on appropriate sections of the Hosgri report and the ASME B and PV code.
As such.the developed criteria should conform with the licensing requirerents -
and are acceptable. ~ -
v Spectra data were .taken from the Hosgri report. The degree _of correspondence between the data and the controlled Hosgri spectra data set is not discussed. For the final qualification of the components considered, the adequacy of the spectra data used must be assessed. The Diablo Canyon Project Interim Technical Program is addressing this issue.
The IDVP identified three generic concerns and therefore recommended additional sampling. The procedures used by the IDVP are acceptable and support _their find.ings. An additional sample should be reviewed as
,4 rec ommended.
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