Letter Sequence Other |
|---|
|
Results
Other: ML18113A966, ML18113A996, ML18114A612, ML18114A720, ML19207B079, ML19224C794, ML19225C064, ML19241B211, ML19246A721, ML19261C984, ML19269D615, ML19289F676, ML19344D736, ML20244A550, ML20244A556, ML20244A647
|
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
[Table View] |
Similar Documents at Surry |
|---|
|
Text
._ *~-.
I
,'.<P'-
l_~~*._./'
DISTRIBUTIO Docket File MAY Docket Nos. 50-280 and 50-281 2 5 1979 a n d ""'l'ail-"'1'.!
NRC PDR (2)
Local PDR _
NRR Rdg
, ORBl Rdg.
V. Stello D. Eiser::ihut R. Vollmer
- B. Grimes W. Russel-1 J. Carter Mr. W. L. Proffttt A. Schwencer Senior Vice President - Power o: N~ighbors Virginia_Electric and Pow~r Compa_ny o. ~Jigginton Post Off1ce Box 26666
Richmond, Virginia 23261 P. Kreutzer OELD I&E (3)
De~r Mr. Proffitt:
TERA J. Buchanan ACRS ( 16)
- 1) *(I a)(Jat,
.:r. /J. /(~lr.i, J...,/Jdlut)
~,/
- d. "
"/3.&~~
The purpose of tnis letter is to state our posit.ion re9ardi119 the "use of,
soil structure'interaction for the seismic pipestress analyses being performed._for *Surry. Power Station, Units l and 2.
Based on the results of the information*you provided by your letter dated May,24, 1979 in response to our May 18, 1979 letter and in other meetings, we confirm that soi 1 structure interaction me tho do 1 ogy may be used for-Surry orovided.that seismic.stresses calculated are increased by a factor of 1.5.
'i°hi s factor applies to the seismic stresses derived from amplified response spectra using 1%.d~mping. *It is further acknowledged that certain individual analyses may require consideration on a ci:1se by case basis.
Th~ earthquake of primary safety concern i's the SSE.
- However, due to the nonlinearities of the soil which are considered in the soil structure interaction analyses, the stiffness of the subgrade is a function of *.the*
earthquake. 1 evel.
Si nee the floor response spectra" are sensitive to the stiffness of the subgrade, they too are dependent on the earthquake l eve 1 *,.Therefore, it is requested that the foll owi.ng two points be addressed;
/
DATIi:~
Discuss in detail why it can be concluded that the pipjng analyzed for the SSE condition will safely withstand all ea_rthquakes up to and including the SSE.
2..
For any pi ping systems which meet SSE_ reqtii rements but do not meet the FSAR *osE design requ*irements, provide the level of f { ~?\\t; ~
-t~* ! -~-(-::.i
~ ~rthquake for~nich _the FSAR OBE design requirements are
'(,.:)tit-met.
J DOR:S&P DOR:EB iHRussell VN09 an Sincerely, 77(),:;,:;--063 i' 0511,,<!79 0
-19 S
"lz u.s. aovttRNMl!!!l:NT P111NT1NG 0PP"1ca: 1111 - ze, - 11a
,,.=
e UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 May 25, 1979 Docket Nos. 50-280 and 50-281 Mr. W. L. Proffitt Senior Vice President - Power Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261
Dear Mr. Proffitt:
The purpose of this letter is to state our position regarding the use of soil structure interaction for the seismic pipestress analyses being performed for Surry Power Station, Units l and 2.
Based on the results of the information you provided by your letter dated May 24, 1979 in response to our May 18, 1979 letter and in other meetings, we confirm that soil structure interaction methodology may be used for Surry provided that seismic stresses calculated are increased by a factor of l.5.
This factor applies to the seismic stresses derived from amplified response spectra using 1% damping.
It is further acknowledged that certain individual analyses may require consideration on a case by case basis.
The earthquake of primary safety concern is the SSE.
However, due to the nonlinearities of the soil which are considered in the soil structure interaction analyses, the stiffness of the subgrade is a function of the earthquake level.
Since the floor response* spectra ~re sensitive to the stiffness of the subgrade, they too are dependent on the earthquake level.
Therefore, it is requested that the following two points be addressed:
- 1.
Discuss in detail why it can be concluded that the piping analyzed for the SSE condition will safely withstand all earthquakes up to and including the SSE.
- 2.
For any piping systems which meet SSE requirements but do not meet the FSAR OBE design requirements, provide the level of earthquake for which the FSAR OBE design requirements-are met.
cc:
See next page Sincerely,
\\.
' (
I
/
r f /.-
t* j
"'- 1 1
t-,,
l I
~*.:.,...;vJJ; )/~(:;,.).J/!.J_,.(),
- 0. G. ::":i senhut, Deputy. Ji rector Division of Operating Reactors.
I
Mr. \\./*. L. Proffitt Virginia Electric and Power Company cc:
Mr. Michael w. Maupin Hunton and Wi 11 iams
- Post Office Box 1535 Richmond, Virginia 23213 Swem Library College of Wil 1 iam and Mary Williamsburg, Virginia 23185 Donald J. Burke U. S. t*luclear Regula-:ory Commission Region JI Office of Inspection and Enforcement 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 e