Letter Sequence Meeting |
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Results
Other: ML18113A966, ML18113A996, ML18114A612, ML18114A720, ML19207B079, ML19224C794, ML19225C064, ML19241B211, ML19246A721, ML19261C984, ML19269D615, ML19289F676, ML19344D736, ML20244A550, ML20244A556, ML20244A647
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MONTHYEARML18113A9961979-03-13013 March 1979
Order to Show Cause Re Potentially Deficient Piping Design. Orders Facility to Be Placed in Cold Shutdown within 48-h
Project stage: Other
ML19282C6771979-03-15015 March 1979
Summary of 790308 Meeting W/S&W to Discuss Pipe Stress Calculations Using Pipestress Code
Project stage: Meeting
ML18113A9671979-03-15015 March 1979
Notification of 790316 & 17 Meeting W/S&W in Bethesda,Md to Discuss Reinstating Operation at Facilities Which Received Shutdown Orders on 790313
Project stage: Meeting
ML18113A9661979-03-20020 March 1979
Summarizes 790320 Telcon W/S&W Re Future Actions to Resolve Outstanding Seismic Concern of Five Shutdown Plants.Requests Reanalysis Results of safety-related Piping Sys & Supports
Project stage: Other
ML19263D8341979-03-26026 March 1979
Discusses 790301 Telcon W/Util & S&W.Nrc Requested Copy of Pipestress Computer Code to Compare W/Nupipe.S&W Stated Policy of Not Releasing Codes or Calculations.Meeting on 790308 for S&W to Bring Pipestress to NRC for Review
Project stage: Meeting
ML18114A5381979-03-29029 March 1979
Assigns Responsibility for Prompt Meeting Notification Re 790313 Show Cause Orders
Project stage: Meeting
ML20244A5561979-03-31031 March 1979
Answer to NRC 790313 Order to Show Cause.Will Reanalyze Seismic Loads on Piping Sys & Will Modify Sys Where Necessary.Expects to Submit Documented Results by 790424. Believes NRC Should Examine S&W Analyses
Project stage: Other
ML20244A5501979-03-31031 March 1979
Forwards Formal Util Response to NRC 790313 Order to Show Cause Re Potentially Unsafe Piping Sys
Project stage: Other
ML19261C9841979-04-0202 April 1979
Forwards Description of Info to Be Documented for NRC Review for Facility.Requests Schedule for Submittal of This Info Prior to Plant Startup
Project stage: Other
ML19344D7361979-04-10010 April 1979
Record of Telcon W/D Ford (Ucs) on 790320 Re Chronology of NRC Activities Re Pipestress Issue
Project stage: Other
ML19289E9721979-04-10010 April 1979
Summary of 790329-30 Meeting W/Util & S&W in Boston,Ma Re Progress to Date & Early Analysis of Pipe Stresses in safety-related Sys
Project stage: Meeting
ML19270G5371979-04-11011 April 1979
Delineates Criterion to Develop plant-specific Info Packages on Site Visits
Project stage: Request
ML20244A6471979-04-17017 April 1979
Licensees Response to 790402 Request of PA Public Util Commission for Hearing & Petition to Intervene Re 790313 Show Cause Order.Urges NRC to Hold Ruling in Abeyance. Certificate of Svc Encl
Project stage: Other
ML19289F0811979-04-20020 April 1979
Summary of 790411-12 Meeting W/Util & S&W in Boston,Ma Re Status of Reanalysis Efforts & Review of Packages Completed to Date
Project stage: Meeting
ML18114A6121979-05-18018 May 1979
Summarizes Procedures & Calculational Techniques Used in Reanalysis of Piping Sys Designed W/Shock II Computer Program.Reanalysis Will Satisfy 790313 Order to Show Cause
Project stage: Other
ML19224C7941979-05-18018 May 1979
Requests Addl Info in Order for NRC to Review Proposed Amplified Response Spectra Using Soil Structure Interaction
Project stage: Other
ML19269D6151979-05-23023 May 1979
Responds to NRC .Forwards Amplified Response Spectra Based on Soil Structure Interaction.Details Result of Analysis of Small Strain Valves of Plus or Minus 50%
Project stage: Other
ML18114A7201979-05-25025 May 1979
Discusses Position Re Use of Soil Structure Interaction for Seismic Pipestress Analyses Being Performed.Approves Methodology,Provided That Seismic Stresses Calculated Are Increased by Factor of 1.5
Project stage: Other
ML19246A7211979-05-25025 May 1979
Submits Identified Areas to Be Addressed During Seismic Pipestress Reanalysis
Project stage: Other
ML19241B2111979-05-25025 May 1979
Discusses Areas to Be Covered in Interim or Final Rept on Seismic Pipestress Reanalysis,Including Stresses Due to Seismic Anchor Movements,Support Stiffness Accountability & Criteria for Pipe Support & Design
Project stage: Other
ML19289F6761979-06-11011 June 1979
Discusses Present Status of Piping Sys Reanalysis.Reanalysis Complete & Two Hydraulic Snubbers Installed.No Pipe Is Overstressed in Event of Safe Shutdown Earthquake.Rept Supporting 790706 Request to Be Submitted by 790618
Project stage: Other
ML19241B8541979-06-14014 June 1979
Summary of 790524 Meeting W/S&W & Util in Bethesda,Md Re Amplified Response Spectra Developed W/Consideration of Soil Structure Interactions
Project stage: Meeting
ML19225C0641979-07-23023 July 1979
Requests Termination of 790313 Order to Show Cause Re safety-related Piping Sys
Project stage: Other
ML19249A7131979-08-0303 August 1979
Draft Safety Evaluation Supporting Resumption of Operation Per Required Mods to Seven Supports,Addition of Three Others & Approval of Two Supports Not Yet Found to Be Acceptable
Project stage: Draft Approval
ML19249A7091979-08-0303 August 1979
Draft Order Not Requiring Continued Shutdown of Facility or Termination Proceeding Initiated by 790313 Order.Analysis & Mod to Fuel Pool Cooling & Purification Sys Required Before Further Use
Project stage: Draft Other
ML19249A7041979-08-0303 August 1979
Forwards for Consideration Draft Order & Draft Safety Evaluation Re Facility Shutdown Per Lack of Assurance That Analysis of Piping Sys for Seismic Loads Provided Proof of Safe Shutdown During Seismic Event
Project stage: Draft Approval
ML19207B0861979-08-0808 August 1979
Safety Evaluation Supporting Order Terminating Proceeding Initiated by 790313 Show Cause Order Re Cold Shutdown Condition.Facility May Resume Power Operation
Project stage: Approval
ML19207B0791979-08-0808 August 1979
Order Terminating Proceeding Initiated by 790313 Show Cause Order Re Cold Shutdown Condition
Project stage: Other
1979-04-02
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UNITED STATES f
.? "
4 NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20556 j
APEll
' 0 1979 Docket No.:
50-334 LICENSEE: Duquesne Light Company FACILITY: Beaver Valley Power Station, Unit No. 1
SUBJECT:
MEETING
SUMMARY
- PIPE STRESS ANALYSIS The licensee and Stone and Webster Engineering Corporation met with the staff on April 11 and 12, 1979 in Boston to discuss the status of the reanalysis efforts and to review the completed packages to-date.
The list of attendees is attached as Enclosure 1.
The review centered on four completed packages (pipe stresses, hanger loads, base plate and bolts) and on seven partially completed packages.
These packages are listed in Enclosure 2.
The review of the systems being reanalyzed resulted in a general but incomplete agreement on the total systems requiring reanalysis. Stone & Webster agreed to provide a complete list of Category 1 piping, a full set of P&ID's, and a line list of all those analyzed by Shock 2, and those safety related. While it was originally thought that about 150 lines were analyzed by Shock 2, S&W has discovered an additional 150 runs which may include earlier duplicates. Therefore, the total runs using Shock 2 is somewhere between 150 and 300. S&W will survey these additional computer analyses to finalize a composite list.
The review of the pipe stress and hanger evaluation packages revealed several areas which were brought to the attention of the licensee.
The packages need a better quality control; the licensee noted that they had accepted only one of the completed packages and quality control The review seems to be was a function that the licensee would perform.
taking a great deal of time. The licensee has noted this to S&W in an effort to maintain their schedule of review. The largest number of problem areas identified from this limited review appears to be on the loading of the anchor bolts of pipe supports. With the information and data being used in the analyses, the seismic effects results in increased loadings on the supports and bolts.
Five problem sets were identified to the licensee as a request for additional information. These problem sets will be used by EG&G-Idaho q 906010 2236 356
3 APRIL
' i' 75 / 9 to perform audit calculations to support our safety evaluation reports.
The problem sets The infomation requested is listed in Enclosure 3.
requested are as follows:
Identification Run Steam Generator Feedwater Line on lA Steam Generator 783 1200 Pressurizer Spray Line 203 Auxilliary Feedwater Suction Line 204 Auxilliary Feedwater Pump Discharge 255A Residual Heat Removal Lines In the conclusion of the meeting, the licensee was requested to advise the NRC at the earliest possible time if a modified amplified response The licensee was spectra was to be used in the Beaver Valley review.
also requested to supply a weekly status of runs report.
Dave Wigginton Operating Reactors Branch #1 Division of Operating Reactors
Enclosures:
As stated 2236 J57 ATTENDEE LIST BEAVER VALLEY - 1 IN BOSTON MEETING WITH NRC, APRIL 11, 1979 Organization Name S&W J. M. Cumiskey S&W Oon King S&W W. J. L. Kennedy DLC N. R. Tonet DLC J. J. Carey EG&G Idaho D. K. Morton NRC W. T. Russell NRC J. M. Giannelli NRC R. G. LaGrange NRC D. L. Wigginton NRC E. V. Imero 2236 358
April 11 & 12,1979 REVIEW - BEAVER VALLEY UNIT #1 Complete Packages
- 1) Auxilliary Feedwater Pump Discharge Lines
- 2) Recirculation Heat Exchanger-River Water Outlet
- 3) Low Head Safety Injection Pump Suction Lines from Sump (Including Sump Cross Tie)
- 4) Reactor Coolant Piping and 8" Crossover Line Between Main Loop Isolation Valves Partial Packages
- 1) Pressurizer Spray
- 2) Steam Generator Feedwater - lA Generator
- 3) Steam Generator Feedwater - 1B Generator
- 4) Steam Generator Feedwater - IC Generator
- 5) Reactor Coolant Piping - lA Loop
- 6) Residual Heat Removal
- 7) Auxilliary Feedwater Lines Suction 2236 359
The following engineering data is required to perform an ANSI B31.1 audit calculation:
1.
List of design and operating temperatures and pressure.
2.
Detailed piping drawings and/or isometrics indicating the geometry of the piping system along with all necessary dimensions (including bend radii) and weld locations.
3.
List of nominal pipe sizes, schedules, weights, insulation weights, and materials.
4.
List of pipe support types, locations, stiffnesses, and preloads (spring hanger hot loads).
5.
List of valve locations, weights, lengths, and eccentricities (center of gravity locations) 6.
List of any anchor movements (thermal, seismic, etc.) and locations.
7.
OBE and SSE response spectra.
8.
Description of any special fittings or components present on the piping system.
9.
Stress summary based on Shock II/Nupipe results.
2236 360