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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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SUMMARY
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Title:
Independent Design Verification Program:
Small Bore Piping Report
, Report No. ITR '30, Revision 0 f
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-INTRODUCTION
-The Interim Technical Report 30 (ITR 30) was prepared by Robert L. Cloud and associates '(RLCA) for the Diablo Canyon Nuclear Power Plant Independent Design Verification Programl(DCNPP-IDVP). The report summarizes the IDVP review of the methods used to qualify small bore piping which is not computer analyzed (span rules) and the field verification of the implementation of these span rules for a sample of small bore systems. The span rules were found to generally satisfy the licensing criteria and to be correctly impl emented.
SUMMARY
OF REPORT A large number of Design Class 1 piping systems in the DCNPP were '
qualified using_ span rules. These rules specify the maximum allowed distance between supports, the span, and provide guidelines for support placement. Two groups of piping _were qualifed by this method. The first group consisted of
- field routed piping 2 inches in diameter or smaller, and the second group consisted of office designed piping with diameters between 2-1/2 and 6 inches.
, Pacific Gas and Electric (PG&E) Drawing No. 049243 " Pipe Supports for Field Run,' Design Class 1 Piping Diablo Canyon" established the span rules for the first group, while PG&E Drawing No. 049239 " Pipe Support Spans for Non-Analyzed Class I Piping Diablo Canyon" established the span rules for the second group.
The methodology implicited in both sets of span rules involves limiting the seismic response of piping systems by controlling the length of spans between, and the placement of, seismic ivpports. The methodclogy is based on enveloped Hosgri floor response spectra with 2% damping and maximum floor eccentricities. Implementation requires the use of enginac.'ing judgment as the rules do not address all possible piping configurations. If properly applied the method yields a fundaaental natural frequency in excess of 15 Hz for the piping system under consideration.
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'The verification included a review of the span rules to establish that
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piping designed to comply with the rules satisfied licensing criteria and c field verification of compliance with the rules. In the review, the para-neters to be'used for the ' sample selection were first established. This included a consideration of pipe size, material properties, design tempera-tures, pressures and natural frequencies. Next, analyses were performed fo^
four small~ bore piping configurations described in the rules (single span, multiple spans, multiple spans with 2 changes in ' direction and an offset case) considering pressure, gravity and seismic loadings and the effects of welded attachments (i.e. , lugs installed to provide axial . constraint). Stresses were then calculated based on equation 12 of ANSI B31.lb 1973, combined and com-pared to the allowables of ANSI B31.1,1973 for both normal conditions and faulted conditions. All analyses for all configurations were not made.
Instead, a representative sample was used. .
The paraneters used in the sample analyzed were chosen to minimize the degree of conservatism in the stress results and or to correspond to prevalence in the field. Summarizing the parameters chosen and the selection criteria:
Sample sizes 2", 3" and 4" because they are widely used.
Schedule 10S and 40 as they gave the lowest natural frequencies.
Allowable stress of 12000' psi and Young's Modulus of 27.7 x 106 psi ,
corresponding to lower strength bound for materials.
- Temperatures of 165*F for S.S. and 200 F for steel corresponding to maximum temperatures.
Pressures of 50 psig and 255 psig for 2", 3", and 4" SCH10S pipe respectively and 700 psig and 1085 psig for 2", 3" and 4" SCH 4G
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pipe respectively corresponding to maximum pressures.
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Uninsulated pipe weight corresponding to span rule limitation.
In addition, for the seismic loading, horizontal and vertical envelope spectra were developed considering Hosgri spectra for elevations at or below 140 feet, in the containment and auxiliary buildings, using maxinum building eccentri-cites.
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The report provides tabulated listings of the results of this review.
Pipe stresses -for small bore piping met the licensing criteria for normal and Hosgri condi t. ions. Some comparisons to results presented in the PG&E Hosgri reevaluation report showe[f that the PGSE stress estimates were higher than those calculated in this review. Lastly, frequency estimates below 15 Hz were noted for several span rule configurations.
Field verification for a sample of three runs of small bore piping, each including more .than twenty supports, was performed. The verification address-ed conformance of as-built conditions to the span rules, documentation of support types, locations ano dimensions, and the reasonableness of the IDVP analysis assumptions. The selected piping was found to be installed in accordance with the span rules. However, pipe routing and suport configura-tions were observed on other pipe runs which were not spccifically addressed ,
by the span rules and were presumable designed by PGSE using engineering judgment. The use of engineering judgment by PG&E in applying the span rules will- be the subject of further IDVP serification following the Diablo Canyon Project corrective action program.
Nine error and open item reports were issued as a result of the span rule review and field inspection, E01's 1024,1043-1048,1058 and 1059. Except for E01's 1058 and 1059 all E0I's were issued to note differences between the field condition and design isometrics. All these were closed as deviations when further review indicated the correct quantities or dimensions were used in the design analyses. E01 1058 was classed a A/B error and was issued to note the possibic exceedance of allowable stresses for certain one or two lug configurations, assuming a ' maximum pipe span. Further analyses showed the stresses to de below allowables. E0I 1059 was classed an error A/B and noted disciepancies in the PGSE repor't, Preliminary Blume Report, and the fact that the span rules did not address insulation weight or 6 inch piping.
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Although the span rules generally satisfied the licensing criteria the following generic concerns were noted: .
The span rules do noi. address insulated' pipe.
The span rules do not limit the areas were small bore piping is installed and may not satisfy _ licensing criteria for high seismic response areas.
The Hosgri report allows the design of 6 inch pipe by the span rules, but these rules do not _ address 6 inch pipe.
The fundamental frequency for _ some span rule configurations are less than 15 Hz.
For 3 and 4 inch pipe, the span rules do-not limit the unsupported distance from a change of direction containing a axially re-strained run of pipe.- ,
A demonstration of'the conservatism of the span rule approach was not presented in the Blume Report, as implied in the Hosgri Repo rt.
In addition, the use of engineering judgement, the verification of maximum vertical and horizontal spans and the field marking of hangers were items noted. All these items and concerns will be addressed by the DCP corrective action program and verifled by the IDVP.
EVALUATION RLCA has made.a reasonable ef fort to assess the adequacy of span rule' criteria. Conservative assumptions, coupled with acceptable analysis techniques were usea to investigate the rules and establish the level of compliance with the licensing criteria. Although every variant allowed by the span rules'was not individually evaluated the bounding cases developed and analyzed seemed appropriate. The RLCA review did reveal and note various deficiencies and omissions in the criteria. The IDVP has committed to the persuance of these until final resolution. Accepting that a comprehensive description of the span rules was provided in the report and assuming that the
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RLCA calculations were correct, the review of these criteria is acceptable and demonstrates their general adequacy.
As may be inferred from the above, two weaknesses in the report are the failure to present the span rules in total and the lack of any real descrip-tion of the models used in their verification. Without this information neither the comprehensiveners or correctness of the verification effort can be assessed. However, past detailed reviews of the RLCA verification ef forts
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have indicated they are both complete and correct.
The field verification performed was limited in scope and designed to verify the implementation of the span rules for pipe runs which matched span rule configurations. However, as stated in the report, numerous examples of pipe routing and support configurations not specifically addressed in the span ,
rules were noted and were presumably designed by the use of engineering j udg aer.t. This observation casts some doubt on the value of this verification e f fo rt. If the exception was the rule, then the fact that the rules are adequate is superfluous. A thorough. evaluation of these exceptions to establish their degree of compliance with licensing criteria must be under-taken to verify the PG&E design of small bore piping. The IDVP has committed to verify this use of engineering judgment by PG&E in applying the span rules following the DCP corrective action program.
One area neglected in this verification was the qualification of the supports used for small bore piping. Obviously these supports must be designed to carry generic, bounding loads, corresponding to the bounding conditions of the span criteria. Since RLCA has developed and analyzed bounding cases the inforration required for the support review should be
. ava il able. It is- anticipated that the IDVP will address this issue in a forthccming ITR en pipe supports (ITR 138). In any case, the verification of the PG&E design of small bore piping by span rules will not be complete mtil a corresponding review of small bore pipe supports is made.
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