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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210A6941999-07-16016 July 1999
Summary of 990628 Meeting with Util in Rockville,Md Re Arkansas Nuclear One,Unit 2 Steam Generator Operational Assessment.List of Meeting Attendees & Licensee Handout Used During Meeting Encl
ML20196J2351999-06-29029 June 1999
Summary of 990617 Meeting with B&Wog & FTI Re B&Wog Emergency Operating Procedure Program.List of Meeting Attendees & Presentation Slides Encl
ML20205J6351999-04-0505 April 1999
Summary of 990303 Meeting with Entergy Operations,Inc in Rockville,Maryland Re Status of Arkansas Nuclear One Backlog for Open Licensing Actions & Activities.List of Meeting Attendees & Licensee Handout Encl
ML20207M9251999-03-11011 March 1999
Summary of 990302 Meeting with Entergy Operations,Inc in Rockville,Md Re Arkansas Nuclear One Steam Generator Insp & Repair Plans for Upcoming Unit 1 Refueling Outage.List of Attendees & Licensee Handout Used at Meeting Encl
ML20198G5501998-12-18018 December 1998
Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop Encl
ML20206S8501998-11-13013 November 1998
Summary of 456th ACRS Meeting on 980930-1002 in Rockville,Md Re Appropriate Action on Items Listed in Attached Agenda
ML20155H3931998-11-0202 November 1998
Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting Attendees Encl
ML20154A0271998-09-25025 September 1998
Summary of 980909-10 Meeting with Entergy Operations,Inc Re Implementation of risk-informed Inservice Insp Program. List of Attendees & Rept Prepared by Structural Integrity Associates,Inc Encl
ML20151X0011998-09-10010 September 1998
Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl
ML20237E1611998-08-25025 August 1998
Summary of 980728 Meeting W/Util in Rockville,Md Re Replacement of SG at ANO Unit 2.List of Attendees & Handouts Encl
ML20236M0501998-07-0808 July 1998
Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl
ML20217K3461998-04-24024 April 1998
Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl
ML20217K5141998-04-24024 April 1998
Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl
ML20217F4811998-03-26026 March 1998
Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl
ML20203B5741998-02-11011 February 1998
Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda Encl
ML20212G8521997-10-29029 October 1997
Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl
ML20211A0161997-09-16016 September 1997
Summary of 970828 Meeting W/B&Wog Re Mgt of Aging Effects for Reactor Vessel Internals & Activities Related to Baffle Bolting Integrity Issues.List of Attendees & Their Affiliation & Handouts Encl
ML20140H9181997-05-0909 May 1997
Trip Rept of 970410-11 Visit to Ul to Observe full-scale Fire Endurance Test of 1 & 3 Hour Versawrap Fire Barrier Sys.List of Participants Encl
ML20137W3311997-04-17017 April 1997
Summary of 970407 Meeting W/Util & Transco Products,Inc Re Versawrap,New Electrical Raceway Firewrap Sys.Attachment 1 Describes Components of Typical Veraswrap Barrier & Attachment 2 Re Transco Products,Inc Test Procedure Encl
ML20149M3611996-12-11011 December 1996
Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl
ML20134M6611996-11-21021 November 1996
Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl
ML20129G4921996-08-29029 August 1996
Summary of 433rd ACRS Meeting on 960808-10 Re Design Changes Proposed by Asea Brown Boveri - C-E Re Certification of Sys 80+ Design,Secy 96-128,proposed Rev 3 to Reg Guide 1.8,revs to Reg Guides 1.84,1.85 & 1.147 & Rev 3 to Reg Guide 1.105
ML20059C4041993-12-27027 December 1993
Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md to Discuss Licensee Proposed Changes to Security Plans for Plant,Units 1 & 2.List of Attendees Encl
ML20058P4491993-12-15015 December 1993
Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md Re 931021 Submittal of Proposed Alternative to 10CFR50.55a(f) & (g),10-Year Inservice Insp & Inservice Testing Update. List of Attendees Encl
ML20058H0351993-12-0808 December 1993
Summary of 930830 Meeting W/Entergy Operations,Inc Re Operation of ANO-2 W/O SG Exam Until Mar 1994 Scheduled Refueling Outage.List of Attendees & Handouts Encl
ML20059A5941993-10-14014 October 1993
Summary of 930929 Meeting W/B&W Re Generic Implications for of Steam Generator Leak for Similar Sleeves Installed at Other Facilities.List of Attendees & Meeting Handouts Encl
ML20056D6661993-06-0101 June 1993
Summary of Operating Reactors Events Briefing 93-19 on 930526
ML20126G0721992-12-22022 December 1992
Summary of 921203 Meeting W/Entergy Operations,Inc Re Results of ANO-2 Steam Generator Tube Exam During Most Recent Scheduled Outage & Licensee Plan for mid-cycle Tube Insp,Scheduled to Begin 930430
IR 05000313/19900081990-08-20020 August 1990
Summary of 900718 Meeting W/Entergy Operations,Inc in Arlington,Tx to Discuss Exercise Weaknesses Identified in Insp Repts 50-313/90-08 & 50-368/90-08
ML20055E9411990-07-0909 July 1990
Summary of 900621 Meeting W/Util Re Proposed Mods for Return to 100% Power.List of Attendees & Viewgraphs Encl
ML20247R0161989-09-21021 September 1989
Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting
ML20245G5421989-08-0303 August 1989
Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247J6991989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl
ML20247J7051989-05-19019 May 1989
Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20195J4291988-11-29029 November 1988
Summary of 881118 Meeting W/Util in Rockville,Md Re Four Plant Startup Issues Including:Dhr Sys Shutdown Cooling Mode of Operation,Operability of Penetration Room Ventilation Sys & Operability of Nozzles in safety-related Piping Sys
ML20206L9831988-11-25025 November 1988
Summary of Operating Reactors Events Meeting 88-45 on 881115.List of Attendees & Handouts Encl
ML20205P2201988-10-26026 October 1988
Summary of 881018 Meeting W/Util in Rockville,Md Re Results of Inservice Insp of Casings of Reactor Coolant Pumps a & B & Request for Relief from ASME Code Requirements for Inspecting Reactor Coolant Pumps.Related Info Encl
ML20204G4391988-10-12012 October 1988
Summary of 880908 Meeting W/Util in Arlington,Tx Re Previous Violation in Area of Contingency Response.Util Expressed Basis for Denial in Insp Rept 50-313/86-34.No New Requirements Imposed But Requirement Already in Place
ML20151Q8131988-08-0303 August 1988
Summary of Operating Reactors Events Meeting 88-031 on 880802.Viewgraphs & List of Attendees Encl
ML20207E2961988-07-28028 July 1988
Summary of 880714 Meeting W/B&W Owners Group Re Industry & NRC Actions to Resolve Issues Raised in Generic Ltr 87-12. List of Attendees,Viewgraphs & B&W Design Differences Encl
ML20150F2451988-06-29029 June 1988
Summary of 880607 Meeting W/Util in Little Rock,Ar Re B&W Owners Group Safety & Performance Improvement Program at Plant
ML20150E0241988-06-21021 June 1988
Summary of 880615 Meeting W/Utils Re Proposed Establishment & Licensing of Sys Energy Resource,Inc as Operators & Licensing Agent for Plants
ML20154S0341988-05-27027 May 1988
Summary of 880519 Meeting W/Middle South Utils Representatives Re Proposed Establishment & Licensing of Middle South Utils Nuclear Operating Co.Agenda Encl
ML20154K9611988-02-0505 February 1988
Summary of 880204 Meeting Re Presentation Made by Allegheny Ludlum on Ferritic Stainless Steel E-Brite
ML20237E0391987-12-0909 December 1987
Summary of 871026 Meeting W/Util Re Permanent Repairs to Pressurizer.List of Attendees & Licensee Handouts Encl
ML20237B4671987-12-0909 December 1987
Summary of 871117 & 18 Meetings W/Util at Plant Site Re Licensee Inservice Testing Program.Licensee Committed to Resubmit Inservice Testing Program in May 1988,pending Closure of Open Items by 880101.List of Attendees Encl
ML20237B4791987-12-0202 December 1987
Trip Rept of 871117 & 18 Visit to Plant Site Near Russellville,Ar Re Pump & Valve Inservice Testing Program. Program Changes Indicated in Response to Questions
ML20236B0861987-10-15015 October 1987
Summary of 871007 Meeting W/Util Re Midcycle Outage on Facility.List of Attendees & Outline of Licensee Presentation Encl
1999-07-16
[Table view]
Category:TRIP REPORTS
MONTHYEARML20140H9181997-05-0909 May 1997
Trip Rept of 970410-11 Visit to Ul to Observe full-scale Fire Endurance Test of 1 & 3 Hour Versawrap Fire Barrier Sys.List of Participants Encl
ML20237B4791987-12-0202 December 1987
Trip Rept of 871117 & 18 Visit to Plant Site Near Russellville,Ar Re Pump & Valve Inservice Testing Program. Program Changes Indicated in Response to Questions
ML20215A7221987-06-11011 June 1987
Trip Rept of 870407-09 Site Visit Re Part of Review of Seismic Design & Tornado Protection of Condensate Storage Tank.Requests Addl Info on Listed Issues Before Assessment of Tank Design Completed
1997-05-09
[Table view] |
Text
. - - _-_
. . . June ll,I 1987 <
4 L
' Docket'No. 50'-313 Mr.-T. Gene Campbell. , i Vice President, Nuclear Operations P. O. Box 551' Little Rock,~ Arkansas. 72203
Dear Mr.- Campbell:
SUBJECT:
SEISMIC DESIGN AND-TORNADO PROTECTION OF
-THE CONDENSATE. STORAGE TANK,'ANO-1
')
On April 7 and 8, 1987, a site visit was conducted by the NRC staff and _. ,
consultants as part of the review of the subject design. In order to complete i t the review we will'need the information identified in the enclosed trip . .
report. Please provide your responses within 60 days of the date of this !
letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, 0MB clearance is not required under P.' L.96-511.
Sincerely, i
l } Sf George F. Dick, Jr., Project Manager
' Project-Directorate - IV 4
Division of Reactor Projects - III, !
IV, V and Special Projects.
Enclosure:
As stated cc w/ enclosure: 3 See next page 1 I
j tDISTRIBUTIONiDockete '
NRC PDR File 4}
Local'PDR"" PD4 Reading D. Crutchfield F. Schroeder
- J. Calvo P. Noonan G.-Dick B. Lee C. Tan 0GC-Bethesda E. Jordan J. Partlow ACRS (10) PD4 Plant File 04/LA P PM PD4/D [
PNoonan Ih k:sr JCalvo fri .
6/cl/87 6 -/87 6/ 11/87 gC B706170050 87061T PDR ADOCK 05000313 P PDR
q Mr'.' G. Campbell-Arkansas Power & Light' Company Arkansas Nuclear One, Unit 1- .j j
- CC: ..
Mr.-J. Ted Enos, Manager
- Nuclear Engineering and Lice., sing L Arkansas Power & Light Company 1 P. O. Box 551 Little Rock, Arkansas 72203 )
i
~Mr. James M. Levine, Director i
Site Nuclear Operations Arkansas Nuclear One l P. O. Box 608 Russellville, Arkansas .72801 Mr. Nicholas S. Reynolds !
Bishop, Liberman, Cook, Purcell & Reynolds !
1200 Seventeenth Street, N.W. !
j Washington, D.C. 20036 l
Mr. Robert B. Borsum -
Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue l Bethesda, Maryland 20814 Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 2090
.Russellville, Arkansas 72801-Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Mr. Frank Wilson, Director Division of Environmental Health Protection Department of Health Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72201 Honorable William Abernathy County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801
.;. e i
" ' ENCLOSURE TRIP REPORT VISIT TO ARKANSAS POWER AND LIGHT COMPANY I APRIL 7-9,1987 l
7-9, 1987. The BNL j A trip was made to Arkansas Power .and Light on April The engineering offices pat $icipants were C.J. Costantino and C.A. Miller. ,
were visited on April 7 and 8,1987 with a site visit made to ANO-1 on April I
(
9, 1987. The objective of the trip was to review the seismic design criteria l The following calculations were used for the Condensate Storage Tank (T-418). l
. reviewed during the visit: I 1, Calc #82-0-2086-08 was performed by NUTECH under contract to APL.
The FLUSH computer code was used to coqute the seismic response of I
the tank / caisson system. The results of this cogutation are design foundation response spectra for both the OBE and SSE earthquakes.
Calc #82-2086-60.was' performed by CBI to evaluate stresses k in the l 2.
tank caused by operational, seismic and tornado loading.. ]
l
- 3. SAR and related Geotechnical data (Arkansas Nuclear One - Foundation, by Bechtel, Oct.1968) describing the site rock and soil properties.
I i:
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- 4. Calc #820-2086-16 by NUTECH describing the loadings used to design l
, the tank foundation and caissons.
i f
The fo11 ming questions were raised during the review of the above material :
and need to be addressed by APL: l NUTECH used a soil shear wave velocity of 1100 fps for the FLUSH j
1.
runs. A review of the geophysical data indicate that this is perhaps closer to the conpression wave velocity, in general, it appears that l
there is a lack of good data for the clay upon which to base the f selection of an appropriate wave speed. f Q
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1
'g 84 > . e A
-2. Poisson's ratio of 0.2 'was used in'the FLUSH' runs for the clay.
review of th'e soil data indicate that the clay is saturated. One would expect the Poisson's. ratio fc,r a saturated clay to be larger than'O.2.
- 3. :The motion developed from the criteria design. spectra was assumed at the surface and. deconvolution methods were used to calculate a consistent bedrock motion.. This bedrock motion was then used as input to the FLUSH program. Since the primary support of the tank (especially'for. vertical and rocking motions) is the caissons which are founded on bedrock, a. more consistent' application'of NRC guidelines would be.to use the criteria motion as input to the base of- the caissons (at bedrock).
- 4. A 10-secohd duration pulse was used as input to the FLUSH model.
1 Response spectra developed from the FLUSH results were then used by.
CBI 'to calculate the effects of water sloshing. :The frequency of the -
sloshing mass was calculated to be about 0.25 cps.. It_ is . questioned !
whether the input spectra, developed from a. ten-second duration pulse, is adequate to' evaluate the response of a 0.25 cps system.
- 5. Respons'e spectra were reported.at the foundation level. These spectra were then used by CBI to evaluate stresses in the tank. 'This ,
approach neglects any inertial that would occur as a result of
- rocking of the' tank. Some rational for_ neglecting this effect is required.
- 6. The CBI calculations do not seem to account for an increase in fluid pressure as a result of the verf.ical seismic input. This increase'in pressure would result in higher hoop stresses in the tank walls.
CBI calculates a wave neight due to sloshing effects which is hip..e l 7.
l than the available f reeboard in the tank. No conc %dion.is given l as tc the potential inpact this may have on the tank design.
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8.- he s'eismic loads used to design the foundaion and caissons are not consistent with the latest seismic analysis.
i I
- 9. The 'CBI report uses 'a Rayleigh-Ritz procedur'e to calculate tank l 1
frequencies. No detail on the asstsned shape function is given and should be provided.
' )
It is recommended that APL be requested to provide additional information on the above issues before an assessment of the tank design is conpleted.
l
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