Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim CollarsML20207D675 |
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ML20207D673 |
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NUDOCS 9903100039 |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 ML20217F3131998-04-17017 April 1998 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 ML20217A8501998-03-19019 March 1998 SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority ML20216J0101998-03-17017 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Relief Request RR-1-18 for Plant ML20198L1151998-01-0808 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 ML20198L4671998-01-0202 January 1998 SER Approving Request for Relief VRR-4B to Inservice Testing Program Wisconsin Electric Power Co,Point Beach Nuclear Plant,Units 1 & 2 ML20197J9341997-12-12012 December 1997 Safety Evaluation Accepting Licensee Request for Relief from Performing Inservice Volmetric Exam of Inaccessible Portions of RPV Lower Shell to Lower Head Ring Weld During 10-yr ISI Interval of Plant,Unit 2 ML20137U4991997-04-10010 April 1997 Safety Evaluation Accepting Proposed Alternatives Contained in Requests for Relief RR-1-17 & RR-2-21 ML20129G6901996-10-0303 October 1996 SER Accepting Request for Relief from ASME Code Repair Requirements for ASME Code Class Three Piping at Plant ML20062J4991993-10-28028 October 1993 Safety Evaluation Granting IST Relief Requests Per 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(f)(4)(iv) ML20062F1361990-09-25025 September 1990 SE Accepting Util Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review - Data & Info Capability ML20248A0101989-09-18018 September 1989 Safety Evaluation Re Containment Liner Leak Chase Channel Venting.Concurs W/Licensee That Plant Does Not Need to Vent Containment Liner Weld Leak Chase Channels During Test ML20246H0121989-07-0707 July 1989 Safety Evaluation Accepting Util 880325 & 1117 Responses to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML20245B0311989-06-14014 June 1989 Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Item 4.5.3 Re on-line Functional Testing of Reactor Trip Sys.Existing Intervals for on-line Functional Testing Consistent W/High Reactor Trip Sys Availability ML20207E4191988-08-0404 August 1988 Safety Evaluation Supporting Compliance W/Atws Rule 10CFR50.62, Requirements for Reduction of Risk from ATWS Events for Light Water Cooled Nuclear Power Plants ML20151R6771988-08-0202 August 1988 Safety Evaluation Granting Request for Relief from ASME Code,Section XI Evaluation Requirements ML20151N2191988-07-27027 July 1988 Safety Evaluation Supporting Util Proposal Re Design of Switchgear Room,Per Sections Iii.G & Iii.L of App R to 10CFR50 ML20150C1311988-06-21021 June 1988 Safety Evaluation Accepting Responses to Generic Ltr 83-28, Item 2.1,confirming That Program Exists for Identifying, Classifying & Treating Components Required for Performance of Reactor Trip Function as safety-related ML20154H5791988-05-12012 May 1988 Safety Evaluation Supporting Conclusions That Rev 1 to Offsite Dose Calculation Manual (ODCM) Uses Methods Consistent W/Staff Requirements,However Some Discrepancies Identified.Odcm & Environ Manual Should Be Revised ML20148H4551988-03-24024 March 1988 Safety Evaluation Accepting Util 840405 Response to Generic Ltr 83-28,Item 2.1,(Part 2) Re Vendor Interface Programs & Reactor Trip Sys Components ML20235K9241987-07-0909 July 1987 Safety Evaluation Re Reactor Pressure Vessel Flaw.Flaw Conditionally Acceptable Per Subarticle IWB-3123 of Section XI of ASME Code & Therefore Requires Augmented Inservice Insps Based on 10CFR50.55(g)(4) ML20213G5801987-05-0707 May 1987 Safety Evaluation Re Util 861027 Request for Relief from Exam Requirements of Section XI of ASME Boiler & Pressure Vessel Code for Shell & Nozzle Welds in Regenerative Hxs. Request Granted ML20206K6011987-04-10010 April 1987 SER Supporting Util 860513 Proposed Replacement of Hydraulic Snubbers W/Energy Absorbers on Main Steam Bypass Line ML20210P2781987-02-0505 February 1987 Safety Evaluation Supporting Util 831107 & 860411 Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability on-line Testing.Plant Designed to Permit on-line Functional Testing of Diverse Trip Features of Breakers ML20214U6081986-11-26026 November 1986 Safety Evaluation Supporting Util 850516 Capsule T Summary Rept Re Use of Reactor Vessel Pressure Temp Limits Specified in Figures 15.3.1-1 & 15.3.1-2 of Tech Specs.Temp Limits Valid & May Continue to Be Used ML20206S7091986-09-16016 September 1986 Safety Evaluation on Util 850426 Response to Open Items Re Generic Ltr 81-14, Seismic Qualification of Auxiliary Feedwater Sys (Afws). Reasonable Assurance Exists That Afws Will Perform Required Safety Function Following SSE ML20214L9311986-09-0404 September 1986 Corrected Safety Evaluation Re Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.Licensee Projections Acceptable ML20207D6781986-07-11011 July 1986 Safety Evaluation Accepting Util Responses to Generic Ltr 82-33 Re post-accident Monitoring Instrumentation Compliance W/Guidelines of Reg Guide 1.97,Rev 2,subj to Listed Condition.Portions of Rev 1 to EGG-EA-6771 Encl ML20138N7801985-10-31031 October 1985 Safety Evaluation Granting Util 840706 Relief Requests for Second 10-yr Inservice Insp Interval.Review of Requests for Relief from ASME Code Section XI Requirements Summarized in Encl Tables ML20134A4821985-10-24024 October 1985 Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Items 3.1.1,3.1.2,4.1 & 4.5.1 Re post-maint Testing (Reactor Trip Sys Components) & Reactor Trip Sys Reliability.Programs Outlined in Acceptable ML20134A6051985-10-22022 October 1985 Safety Evaluation Re Util 831107 & 850910 Responses to Generic Ltr 83-28,Item 1.1, Post-Trip Review Program Description & Procedures. Program & Procedures Acceptable ML20138H1721985-10-18018 October 1985 Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing ML20133G4171985-07-29029 July 1985 Safety Evaluation Accepting Util 831108 Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review.Response to Listed Deficiencies,Including Development of Systematic Safety Assessment Program for Unscheduled Reactor Trips Required ML20129H7871985-05-16016 May 1985 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re Reactor Trip Sys Reliability,Provided Corrective Action Taken If Higher than Normal Valves Observed in Trip Force & Response Time Values ML20205H2171984-09-10010 September 1984 Supplemental Safety Evaluation Re Util 820820 & 860113 Requests for Relief from Inservice Insp Requirements. Volumetric Exam Acceptable Method for Detecting O.D. Initiated Flaws.Relief from Surface Exams Should Be Granted ML20204F5381983-04-25025 April 1983 Safety Evaluation of Util Preferred Ac Power Sys Conformance GDC 17.Proximity of Low Voltage Transformers Does Not Fully Meet GDC 17 Requirements for Physical Separation,But Deluge Sprinkler Sys Adequate 1999-09-15
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARNPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0008, Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with1998-12-31031 December 1998 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 NPL-98-1006, Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20195J5101998-11-16016 November 1998 Proposed Revs to Section 1.3 of FSAR for Pbnp QA Program ML20198J5941998-11-0303 November 1998 1998 Graded Exercise,Conducted on 981103 NPL-98-0948, Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With NPL-98-0880, Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored1998-10-21021 October 1998 Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored ML20154M9121998-10-14014 October 1998 Unit 1 Refueling 24 Repair/Replacement Summary Rept for Form NIS-2 ML20154L6751998-10-14014 October 1998 Unit 1 Refueling 24 ISI Summary Rept for Form NIS-1 NPL-98-0826, Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20151W3851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbnp Units 1 & 2 NPL-98-0653, Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4471998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 2 ML20151W4541998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 1 ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 NPL-98-0558, Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 2 ML20151W4261998-06-30030 June 1998 Corrected Page to MOR for June 1998 for Pbnp Unit 2 ML20151W4221998-05-31031 May 1998 Corrected Page to MOR for May 1998 for Pbnp Unit 2 NPL-98-0481, Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4011998-04-30030 April 1998 Corrected Page to MOR for April 1998 for Pbnp Unit 2 NPL-98-0356, Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20217F3131998-04-17017 April 1998 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 ML20216D7071998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3981998-03-31031 March 1998 Corrected Page to MOR for March for Pbnp Unit 2 NPL-98-0209, Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable1998-03-30030 March 1998 Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable ML20217A8501998-03-19019 March 1998 SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority ML20216J0101998-03-17017 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Relief Request RR-1-18 for Plant NPL-98-0159, Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3891998-02-28028 February 1998 Corrected Page to MOR for Feb 1998 for Pbnp Unit 2 ML20216D7121998-02-28028 February 1998 Revised Corrected MOR for Feb 1998 for Point Beach Nuclear Plant,Unit 2 NPL-98-0084, Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 21998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20198L1151998-01-0808 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 1999-09-30
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UNITED STATES j' , :r NUCLEAR REGULATORY COMMISSION L WASHINGTON, D.C. 30000 4001 ASSESSMENT OF THE DESIGN INFORMATION ON PIPING RESTRAINTS WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 l
l DOCKET NOS.60-266 AND 50-301
1.0 INTRODUCTION
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- By letter dated April 16,1998, the staff informed Wisconsin Electric (WE or licensee) that it wan l performing a review of records related to the design of restraints on the main steam (MS) piping
- and primary loop auxiliary piping systems at the Point Beach Nuclear Plant (PBNP). ' Specific i requests for information were included in an enclosure to that letter. On June 15,1998, the licensee responded to the request for information based on availab!e records and the licensee i staff's recollection of original design aspects requested in the NRC staff's inquiry. As a follow-j up to this assessment activity, the staff visited WE corporate offices on October 15 and 16,
! 1998, to review relevant design records and interview licensee representatives. Duke
- Engineering and Services (DE&S) was recently contracted by WE to perform an independent j evaluation of the existing MS piping at PBNP to confirm the adequacy of restraint design in the
- MS piping system.
2.0 DISCUSSION
! 2.1 Main Steam Pioina i
j The licensee analyzed the MS piping for high energy line break (HELB) scenarios inside the
. Unit 1 and Unit 2 containments at PBNP. This evaluation was performed to assess the impact
- of removing various shim collars from the original Unit 2 pipe whip restraint design. The 4 evaluation utilized criteria contained in Generic Letter (GL) 87-11 (" Relaxation in Arbitrary l Intermediate Pipe Rupture Requirements") to determine postulated break Irt.ations on the
! piping. In accordance with GL 87-11, licensees may eliminate intermediate .o re breaks when i pipe stresses are within specified acceptance limits. Review of the pipin'a @ ass analysis 4 reports for the MS piping inside containment indicates that the stresses in affected piping are j below the limits established in GL 87-11, and consequently, only the terminal endpoints required evaluation for HELBs in the MS piping inside containment.
The methodology utilized to evaluate the consequences of an HELB in the MS piping in this
- analysis is consistent with the criteria established by Bechtel for the original plant design. This
- method employs a concentrated blowdown force (originally developed by Westinghouse) equal i to the pressure multiplied by the intemal area of the pipe that is applied statically at the break ~
4 location. The piping system is then evaluated for plastic hinge formation as well as for the
- effects on the piping system.-
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i 9903100039 990222 PDR ADOCK 05000266 -
P pop e ENCLOSURE'
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1 1
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DE&S utilized the "AutoPIPE" computer program to perform an elastic analysis of the MS piping for a guillotine failure at the SG MS nozzle and the containment penetration anchor. This ,
computer program has been adequately benchmarked and has been accepted by the NRC for I similar applications. The analytical results were reviewed to determine whether plastic moments are developed in the system. If no plastic hinges are formed, then the system is stable and the piping is acceptable. If a plastic hinge is formed, then a moment-less hinge connection is modeled at that point, and the analysis is repeated based on the modified geometry and boundary conditions. The force applied to the terminal end for the second run is l equal to the original blowdown load minus the load required to form the initial plastic hinge. The l results of the second run are superimposed upon the results of the initial analysis, and then reviewed for development of additional plastic hinges. If no additional hinges are formed, the piping model is considered stable and deemed acceptable. If an additional hinge forms, further reanalysis would be required.
In the evaluation of the MS piping for a guillotine break at the containment penetration, the Unit 2 Loop B MS piping system was used as an enveloping case. A plastic hinge developed near one whip restraint due to a load less than the Bechtel tJowdown force. The result from the second run (including the plastic hhge in the model) was superimposed onto the results from the initial analyses. The combined results indicate that no additional plastic hinges will form in the piping. Therefore, the piping system was determined to be acceptable for the containment penetration guillotine break scenario.
Evaluation of the MS piping for a guillotine break at the SG MS nozzle addressed the deleted shim collars in the Unit 2 failure restraints. The Loop B MS piping system was again used as an enveloping case. A plastic hinge developed at an elbow as a result of a load less than the Bechtel blowdown force. Further evaluation identified that an additional plastic hinge will form at the snubber support upstream of the first hinge. This condition required additional analyses to be performed, as described below.
The jet loads required to develop the initial hinge on each MS piping loop (Unit 1 A/B and Unit 2 ,
A/B) were also determined. These loads were used to perform a nonlinear inelastic analysis to '
determine the rotation of the plastic hinge using an energy balance method. An energy balance of the plastic moment capacity of the hinge is equated to the energy in the system due to the fore applied to the overhung segment of piping from the break location at the SG nozzle to the location near the snubber supports where the initial plastic hinge formed.
Two cases were considered for the energy balance evaluation:
I Case 1 assumed no singla active failures occur and a limited fluid reservoir is available in the system; j
- Case 2 assumed a single active failure of the MS check valves,in the SG foop. This scenario provided an essentia!!y unlimited fluid reservoir from the opposite SG which j caused a sustained jet force to exist.
The energy balance evaluation used a 3-step time history considering an " initial" blowdown force, a " transitional" blowdown force, and a
- steady state" blowdown force. The blowdown forces developed in the time history were based on theoretical and testing data available with DE&S, as well as in supplemental technical procedures used for pipe rupture analysis and design in the 1978
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through 1983 time period. This data has been previously reviewed and found to be acceptable by the NRC staff. The initial and transitional blowdown forces were dependent on the pipe dimensions, and the pipe configuration from the break location to the fluid reservoir or an intermediate flow restriction. The steady-state blowdown force is dependent on the system frictional flow losses from the break location to the flow reservoir or an intermediate flow restriction.
The time history was used as a basis for the development of a single blowdown thrust force to be ,
used for the two phases of pipe whip motion: (1) the fluid accelerating the pipe from zero to a !
maximum velocity, and (2) the hinge decelerating the piping from a maximum velocity back to
]j zero. These pipe movements determined the input inelastic energy and this energy was compared 1
to the energy needed for hinge rotation where all energy is conservatively absorbed. The overhung beam model was used to determine the rotation of the plastic hinge.
'l The snubber loads generated in Case 1 were determined to be less than the design loads provided by Bechtel. The system is therefore considered stable and the piping is acceptable. The rotational path of the plastic hinge was reviewed to verify that the jet loads do not impact critical ,
l systems / equipment. However, the energy developed as a result of the initial blowdown force in Case 2 is suffacient to rotate the plastic hinge in the piping system. This second case also includes a steady-state load remaining in the system after rotation of the hinge. Hence, a supplemental analysis was performed to determine additional formation of hinges. The results from this i 1
supplementary analysis determined that no further plastic hinges will form in the system.
Therefore, the system was considered stable and the piping was determined to be acceptable for the guillotine break at the SG nozzle.
i Based on its review of the licensee's summary of reanalysis of the MS piping and interviews with !
licensee staff, the staff concludes that the licensee provided adequate justification that the existing l MS piping system and restraints inside containment at PBNP Units 1 and 2 are structurally j adequate and meet current licensing and design-basis requirements. On the basis of its assessment as discussed above, the staff believes the licensee provided a reasonable justification regarding the deletion of shim collars in the MS piping.
2.2 Auxiliary Pioina The staff examined records relating to the licensee's implementation of IE Bulletin 79-14 (" Seismic Analyses for As Built Safety-Related Piping Systems") for the auxiliary piping system. The records indicate that the licensee has completed the piping reverification program to satisfy the requirements of IE Bulletin 79-14 for safety-related piping at PBNP. The purpose of this program was to compare and reconcile the as-built pipo routing and support configurations against the l
design records. A total of 139 subsystems have been evaluated since the program was initiated in 1991, comprising almost 3000 piping supports and more than 36,000 feet of pipe. Fourteen subsystems in the original scope were dropped from the analysis effort in 1996 when the piping ,
was identified as nonsafety-related, independent contractors performed the piping reverification programs related to IE Bulletin 79-14 for the licensee. As-built walkdowns of selected relrod piping were completed by the licensee in 1996, with the exception of some of the RHR (residual heat removal) subsystems, which were added to the scope and completed in 1997. The majority of piping analyses were completed by the first half of 1998. The NRC regional staff followed the licensee's implementation program for IE Bulletin 79-14 and found it acceptable as discussed in a number of reports issued during the
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' -4 period between 1991 and 1998. The overall modification rate for the program, which includes support upgrades, was approximately 8 percent.
The staff believes the implementation of thic program provides reasonable assurance to conclude that the as built auxiliary piping and support installation are structurally adequate.
3.0 CONCLUSION
in summary, the staff concludes that the licensee was unable to retrieve the original analyses that may have been performed to justify the removal of the shim collars in the early 1970s, and hence, the staff cannot conclude whether or not their removal was justified in consideration of the licensing basis requirements at that time. However, based on the recent evaluations of the MS piping examined by the staff, the licensee has provided adequate technical justification for the removal of certain shim collars in the MS piping restraints. The staff also finds that the licensee '
has provided reasonable basis to confirm the structural adequacy of the current as built configuration of the MS and auxiliary piping systems.
Principal contributor: Jai Rajan Date: February 22, 1999 i
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