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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17329A1471991-08-30030 August 1991 Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1991.W/o Encl ML20055C6081990-05-16016 May 1990 Responds to Outlining Concerns Re Info Notice 88-056, Potential Problems W/Silicone Foam Fire Barrier Penetration Seals. Silicone Foam Acceptable Matl Provided Certain Installation Parameters Controlled ML18037A3791982-05-27027 May 1982 Forwards Annual Financial Repts 1981 for Niagara Mohawk Power Corp,Ny State Electric & Gas Corp,Lilco,Rochester Gas & Electric Corp & Central Hudson Gas & Electric Corp ML20003H2821981-04-30030 April 1981 Forwards Resolutions of SER Issues 10,11,12,40,41,42,49 & 56.Also Forwards Annual Financial Repts 1979 & 1980 ML19338F4861980-10-10010 October 1980 Notifies That Future NRC Correspondence Re Facilities Should Be Addressed to Cj Davis ML19347C0541980-10-0808 October 1980 Forwards Petition for Rehearing in Case 80003 Re Application for Certificate of Environ Compatibility & Public Need. Certificate of Svc Encl ML19338E5731980-09-30030 September 1980 Informs That Correspondence for Nuclear Responsibilities Should Be Addressed to Ms Pollock ML19338F6191980-09-16016 September 1980 Responds to IE Bulletin 80-20, Failure of Westinghouse Type W-2 Spring Return to Neutral Control Switches. Westinghouse Has Not Fabricated Any Control Cabinets for safety-related Equipment Using Specified Switches ML19351D6041980-09-10010 September 1980 Comments on Proposed Rules 10CFR50 & 51 Re Statement of Interim Policy on Nuclear Power Plant Accident Considerations Under Nepa.Supports Commission Approach as Interim Guidance ML19338E6701980-08-20020 August 1980 Responds to IE Bulletin 80-16.Plant Design Does Not Include Rosemount Model 1151 & 1152 Pressure Transmitters ML19330C3081980-08-0101 August 1980 Responds to D Eisenhut 800702 Ltr Re Estimates of Evacuation Time for Site.Info Will Be Developed Upon Receipt of Ny State Board on Electric Generation Siting & Environ Certification ML19320D5541980-07-0101 July 1980 Responds to IE Bulletin 80-08 Re Containment Liner Penetration Weld Examinations.Penetrations Will Be Fabricated Per Reg Guide 1.19.Butt Welds Will Be Radiographed ML19318C0131980-06-12012 June 1980 Requests Verification of Address.Related Correspondence ML19318C1271980-06-0505 June 1980 Responds to IE Bulletin 80-05, Vacuum Condition Resulting in Damage to Chemical Vol Control Sys (CVCS) Holdup Tanks. Engineering Activities Have Been Curtailed to Point Where Detail Design Data Requested Is Unavailable ML19318B0361980-05-28028 May 1980 Responds to IE Bulletin 79-03A, Longitudinal Weld Defects in ASME SA-312 Type 304 Stainless Steel. All Westinghouse- Supplied Pipe for Use on NSSS Is Either of Forged Seamless or Centrifugal Cask Const ML18037A2561980-05-19019 May 1980 Forwards Annual Financial Repts,1979 for Central Hudson Gas & Electric Corp,Long Island Lighting Co,Ny State Electric & Gas Corp & Rochester Gas & Electric ML19309E4301980-03-19019 March 1980 Responds to IE Bulletin 80-03.Charcoal Adsorber Cells Have Not Been Purchased ML19309D0781980-02-26026 February 1980 Comments on Proposed Rule 10CFR50 on Behalf of Suffolk County,Ny:Emergency Planning Must Be Viewed as Equivalent Rather than Secondary to Siting Design in Achieving Public Protection ML19296D6701980-02-0707 February 1980 Responds to IE Bulletin 79-28, Possible Malfunction of Namco Model EA180 Limit Switches at Elevated Temps. No Switches Purchased Yet.If Purchased,Suitable Controls Will Be Instituted ML19322D7141980-02-0101 February 1980 Advises of Ny State Board on Electric Generation Siting & Environ 800129 Denial of Lilco Application for Const of Facility at Jamesport,Ny ML19320C8011980-01-23023 January 1980 Requests That NRC Amend Proposed Regulation Re Formulation of Evacuation Plan to Include All Territory East of Facility.Proposed 10-mile Radius Is Unworkable for People of Long Island.Responsible Plan Should Be Developed ML19305B4501980-01-23023 January 1980 Comments on Proposed Rule 10CFR50:commends NRC for Taking Action Re Evacuation Plan as Need for Comprehensive & Uniform Policy Is Long overdue.Ten-mile Radius Would Be Unworkable in New York City & Should Be Reconsidered ML19290D0331980-01-11011 January 1980 Responds to IE Bulletin 79-02,Revision 2.Expansion Anchor Bolts Will Not Be Used in Concrete Block Walls to Attach Piping Support of Seismic Category I Sys.Steel Members Will Not Be Attached Directly to Concrete Walls ML19284A8091980-01-0707 January 1980 Responds to IE Bulletin 79-25, Failure of Westinghouse Bfd Relays in Safety-Related Sys. No Westinghouse Relays Used or Planned for Use in safety-related Sys ML19260E1341979-12-14014 December 1979 FOIA Request for Documents Re Jamesport Nuclear Power Station,Units 1 & 2 ML19254F2641979-11-0202 November 1979 Discusses Brookhaven Draft Rept on Response Combination. Mark II Owners Group Suggests Criteria Should Include Provisions for Application to Load & Response Levels ML19250C3951979-10-29029 October 1979 Responds to IE Bulletin 79-14, Seismic Analyses for As-Built Safety-Related Piping Sys. Safety-related Sys Not Seismically Analyzed Because of Const to Start in 1982.Insp Will Be Done According to Util QA Program ML19256F1591979-10-29029 October 1979 Responds to IE Bulletin 79-23.Purchase Order for Emergency Diesel Generators Has Not Been Placed.Will Ensure Compliance by Testing Generator During Preoperational Test Program ML19276G9001979-08-18018 August 1979 Informs That No Security Training & Qualification Program Is Presently Being Developed.Due to Current Project Schedule, Program Would Be Premature ML19274G1351979-07-20020 July 1979 Responds to IE Bulletin 79-11.Purchase Orders for Circuit Breakers in safety-related Sys Not Placed. Particular Circuit Breakers to Be Used Are Unknown ML19242B2601979-07-0606 July 1979 Submits Response to IE Bulletin 79-02,Revision 1,re Plant Design.Info Pertains to Project Design Procedure & Spec for drilled-in Anchors,Cyclic Loadings & Pipe Support Base Plate Configurations ML19247A2961979-06-12012 June 1979 Responds to IE Bulletin 79-09.Purchase Orders for Circuit Breakers in safety-related Sys Have Not Been Placed.If GE Type AK-2 Circuit Breakers Are Used,Preventive Maint Program Will Be Conducted ML19269E9111979-05-30030 May 1979 Responds to IE Bulletin 79-07.No Seismic Stress Analyses of safety-related Piping Have Been Performed.Intends to Use Nupipe Computer Program for Piping Analysis ML19224D4281979-05-28028 May 1979 Forwards Suffolk County,Ny Legislature Opposing Facility Const ML19276G6421979-05-28028 May 1979 Forwards Resolution 474,adopted by County Legislature of Suffolk County,Ny in Opposition to Plant Const ML19242B4151979-05-25025 May 1979 Responds to IE Bulletin 79-04.No Purchase Orders Issued for Swing Check Valves.Qa Program Vendors W/Acceptable Method for Determining & Verifying Correct Valve Weights Will Be Selected ML19269E9001979-05-11011 May 1979 Responds to IE Bulletin 79-03.Station Design Reviewed & Welded Pipe Is Not Used in Westinghouse NSSS ML19246C0611979-05-10010 May 1979 Notifies That Suffolk County,Ny Legislature Passed Resolution Opposing CP Sought by Util ML19289E7851979-04-13013 April 1979 Requests Inclusion of Ny Dept of Public Svc on Svc List for Ny Siting Proceeding ML19274E6201979-03-0909 March 1979 Forwards Updated 1978 & 1979 Peak Load Forecasts of Long Island Lighting Co & Ny State Electric & Gas Corp.Also Compares Applicants' 1979 Forecasts to Total Controlled Sources & Required Capability for 1988-1992 ML20062H0441979-03-0808 March 1979 Forwards IE Bulletin 79-02, Pipe Suport Base Plate Designs Using Concrete Expansion Anchor Bolts ML19296A4551979-02-14014 February 1979 Ack Receipt of 790208 Ltr Advising of Classified Document Re Issue of Sabotage of Spent Nuclear Fuel at Facility.Requests Aid in Bringing Draft Document to Attention of Local Law Enforcement Officials ML19269C9981979-01-26026 January 1979 Advises of 790122 Prehearing Conference & Sets Schedule for Upcoming Evidentiary Hearings on Reopened Issues.Siting Board'S Order Directing Remand Requires Decision by Sept 1979 ML19274D3561979-01-19019 January 1979 Forwards Final Rept on Archaeological Salvage Excavation at Hallock'S Pond Site,Nov 1978.Encl Available in Central Files ML19270F5861979-01-12012 January 1979 Ack Receipt of ASLB Initial Decision.Requests Detailed Studies Used as Basis for Decision on once-through Cooling Sys ML19259A7081979-01-0505 January 1979 in Response to NRC 781206 Ltr,Util States They Have Been Complete & Accurate in Submittals & Prompt in Correcting Errors.If NRC Disagrees,Examples Should Be Cited ML19259A6001979-01-0202 January 1979 Requests Issuance of Const License Pursuant to Initial Decision of ASLB Dtd 781226.Forwards Payment of Licensee Fee Under Protest & Payment Shall Not Be Deemed Waiver of Applicant'S Rights to Seek Refund ML19282C3131978-12-27027 December 1978 Forwards 781222 Order Directing Remand,Reopening Jamesport Record on Issues of Need,Comparative Economics & Alternatives.W/O Encl ML19305A0801978-12-0707 December 1978 Advises That Ny State Board on Electric Generation Siting & the Environ Reopened Hearing Record on 781121.Board's Decision Will Be Forwarded to Aslab ML20062G3981978-12-0606 December 1978 Emphasizes Importance of Submitting Accurate & Complete Info to NRC by Licensee & Applicants.Info Submitted Must Be Substantiated by Data & Calculations.Licensee Must Notify NRC of Any Inaccuracies or Enforcement Action Will Result 1991-08-30
[Table view] Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20197E5561980-02-0707 February 1980 Submits Reasonable Values for CP Environ Review Charges, Based on NRC Computer Printouts of Charges,Examination of Lab Monthly Repts & Info from Anl ML20062E6651978-11-16016 November 1978 Forwards Recent Memos Discussing Problems W/Pipe Support Base Plate Design,Applicable to Subj Facil.W/Encl ANO: 7811020332,7811020343 & 7811020336 ML20204C9231978-11-0808 November 1978 NRC Has No Objections to Applicant or County of Suffolk'S Motions to Correct Transcript, & 781103, Respectively ML20197C4521978-11-0606 November 1978 States That the Staff Objects to Certain Charts Being Considered as Evidence Since They Were Not Offered as Such Originally & Are Untested by cross-examination ML20148E1021978-10-20020 October 1978 Forwards 780929 Memo from Director of NRR to Commissioners Re Results of Recently Conducted Fire Protection Research Tests by Ul for NRC Fire Protection Research Program ML20147D2501978-10-0505 October 1978 Reports Staff View That Oral Argument & Site Inspec of Subj Facility Should Continue as Scheduled ML20147D2011978-10-0202 October 1978 Advises Author Will Represent NRC Staff W/Encl Notice of Appearance ML20198F1861975-02-21021 February 1975 Informs of Issuance of CP-stage Dess for Listed Facilities. Schedule for Review & Comments on Dess,Including Lead Responsibilities for Assembling Inputs,Provided ML20198G2671975-01-22022 January 1975 Forwards Rev to Draft Input to Section 13.1 of Input to SER Re Review of PSAR Chapter 13 & 14.Rev Reflects Reorganization of Facility Submitted in 750109 Amend 14 1980-02-07
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20197E5561980-02-0707 February 1980 Submits Reasonable Values for CP Environ Review Charges, Based on NRC Computer Printouts of Charges,Examination of Lab Monthly Repts & Info from Anl ML20062E6651978-11-16016 November 1978 Forwards Recent Memos Discussing Problems W/Pipe Support Base Plate Design,Applicable to Subj Facil.W/Encl ANO: 7811020332,7811020343 & 7811020336 ML20204C9231978-11-0808 November 1978 NRC Has No Objections to Applicant or County of Suffolk'S Motions to Correct Transcript, & 781103, Respectively ML20197C4521978-11-0606 November 1978 States That the Staff Objects to Certain Charts Being Considered as Evidence Since They Were Not Offered as Such Originally & Are Untested by cross-examination ML20148E1021978-10-20020 October 1978 Forwards 780929 Memo from Director of NRR to Commissioners Re Results of Recently Conducted Fire Protection Research Tests by Ul for NRC Fire Protection Research Program ML20147D2501978-10-0505 October 1978 Reports Staff View That Oral Argument & Site Inspec of Subj Facility Should Continue as Scheduled ML20147D2011978-10-0202 October 1978 Advises Author Will Represent NRC Staff W/Encl Notice of Appearance ML20198F1861975-02-21021 February 1975 Informs of Issuance of CP-stage Dess for Listed Facilities. Schedule for Review & Comments on Dess,Including Lead Responsibilities for Assembling Inputs,Provided ML20198G2671975-01-22022 January 1975 Forwards Rev to Draft Input to Section 13.1 of Input to SER Re Review of PSAR Chapter 13 & 14.Rev Reflects Reorganization of Facility Submitted in 750109 Amend 14 1980-02-07
[Table view] Category:NRC TO ASLAP
MONTHYEARML20062E6651978-11-16016 November 1978 Forwards Recent Memos Discussing Problems W/Pipe Support Base Plate Design,Applicable to Subj Facil.W/Encl ANO: 7811020332,7811020343 & 7811020336 ML20204C9231978-11-0808 November 1978 NRC Has No Objections to Applicant or County of Suffolk'S Motions to Correct Transcript, & 781103, Respectively ML20197C4521978-11-0606 November 1978 States That the Staff Objects to Certain Charts Being Considered as Evidence Since They Were Not Offered as Such Originally & Are Untested by cross-examination ML20148E1021978-10-20020 October 1978 Forwards 780929 Memo from Director of NRR to Commissioners Re Results of Recently Conducted Fire Protection Research Tests by Ul for NRC Fire Protection Research Program ML20147D2501978-10-0505 October 1978 Reports Staff View That Oral Argument & Site Inspec of Subj Facility Should Continue as Scheduled ML20147D2011978-10-0202 October 1978 Advises Author Will Represent NRC Staff W/Encl Notice of Appearance 1978-11-08
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* * & UNITED STATES
%,k NUCLEAR REGULATORY COMMiss!ON WASHINGTON, 0. C. 20555 f :,, [
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- Jerome E. Sharfman, Esq., Chairman W. Reed Johnson Atomic Safety and Licensing Appeal Atomic Safety and Licensing Appeal Board Board U.S. Nuclear Regulatory Comission '
U.S. Nuclear Regulatory Comission Washington, D. C. 20555 Washington, D. C. 20555 Richard S. Salzman, Esq.
Atomic Safety and Licensing Appeal Board hkjj, e r, U.S. Nuclear Regulatory Comission j <,! 4 _
Washington, D. C. 20555 y _.
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In the Matter of . E V,1 '
2 LONG ISLAND ly=J' .TIJ* G COMPANY t ??
(Jamesport Nuclear P,cwer Stahion, Units 1 & 2)Y.'s:- -Y- e9' Docket Nos? 50-516 & 50-517 V:)y Gentlemen: - Q N o..'
Enclosed are recent memoranda discussing certain problems experienced in connection with pipe support base plate design. The Nuclear Reactor Regulation staff has infonned us that the problems discussed in Mr.
Stello's memorandum dated September 28, 1978 are applicable to the proposed Jamesport facility, and that the Division of Systems Safety is presently reviewing this aspect of piping design analysis on a case-by-case basis unde ~r SRP section 3.9.3 - ASME Codes 1, 2 and'3 Components,' Component Supports and Core Support Structures. If the Board or any of the parties
(_ wish additional information, please let us know. ,
Sincerely, r -
,M ernard M. Bordenick Counsel for NRC Staff Enclosure as Stated cc (w/encls.):
Sheldon J. Wolfe, Esq. Dr. Harris Fischer Ira Lee Zebrak, Mr. Ralph S. Decker Irving Like, Esq. Dr. Arthur Tampi Dr. E. Leonard Cheatum Mrs. Laetitia deK. Bradley Jeffrey Cahen, E.
Edward J. Walsh, Jr. , Esq. Ms. Shirley L. Bachrach W. Taylor Reveiey, III, Esq. Ms. Adelaide Flatau Mr. A. E. Kintigh William C. Chapek Environmental Protection and Joseph C. Gramer, Esq.
Progress Committee Carl G. Dworkin, Esq.
Dr. Caryl R. Granttnam Frederick H. Lawrence, Esq.
Ms. Jean H. Tiedke Atomic Safety & Licensing Appeal Panel 7g ocketin and Service Section Atomic Safety & Licensing Soard Panel
. , 48 '% UNITED STATES-d)( /k NUCLEAR REGULATORY COMMisslON
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MEMORANDUM FOR: Milton J. Grossman, Hearing Division b Director and Chief Counsel, OELD
% v FROM: Victor Stello, Jr. , Director Division of Operating Reactors. NRR -
SUBJECT:
BOARD NOTIFICATION - PIPE SUPPORT BASE PLATE DESIGN s
The attached memorandum to Roger Mattson, dated June 28, 1978, presents information concerning failures of safety-related pipe supports at Millstone 1 and design deficiencies on similar equip-ment at Shoreham Unit 1. As indicated in the attachment, two factors appeared to contribute to failure of anchor-bolt connec-tions of pipe supports. These are,1) the design assumption that base plates perform structurally as rigid load-bearing members when they may be flexible members, and 2) incorrect anchor bolt torquing.
Recent audits of Architectural Engineering firms and assessments of the actions taken at Millstone, as noted in the attachment, provided the following general information:
- 1. During the last few years, the A/Es have changed their design and installation procedures for concrete embedded pipe supports.
- 2. Past and current design and installation procedures vary among the A/Es.
3 In the past many of the pipe support designs have been con-tracted, and were done with methods not known by the principal A/Es.
We have concluded that the more detailed information required must be obtained from each operating facility. We are preparing a generic
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Milton J. Grossman letter to each operating facility requesting detailed design, installation, and testing information of concrete-embedded anchor-bolted pipe supports of safety-related equipment.
We recommend that this information be provided to the following Boards:
- 1. Monticello (FTL)
- 2. Indian Point 1,2,3 (Seismic Design)
We will provide an assessment of this issue upon completion of
'_ our evaluations. .
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Victor Stello, Jr., Director Division of Operating Reactors Office of Nuclear Reactor Regulation
Enclosure:
June 28, 1978 memo, Stello to Mattson cc w/ enclosure:
D. Vassallo
- V. Stello R. Mattson R. Bevan L. 01shan
. L. Nichols V. Noonan A. Schwencer T. Ippolito -
J. Fair
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MEMORANDUM FOR: B. X. Grimes, Assistant Director for Engineering and Projects, DOR 8,, \ WI k '
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D. G. Eisenhut, Assistant Director -
for Systems and Projects, DOR g\CN a
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Acitng Branch Chief, p#a%M
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Engineering Branch, DOR b SUBbCT: PIPE SijPPORT BASE PLATE PROBLEM % y
. The Engineering Sranch, Division of Operating Reactors, has contacted Bechtel, Bergen - Paterson, Gilbert, and Stone & Webster in regard to their past and current design procedures for support base plates '
utilizing drilled anchor bolts. Bechtel and Stone & Webster indicated that they became aware of base plate flexibility effects on anchor bolt pull-out loads within the past couole of years and are now considering this in current designs. C:7 cert and Bergen - Paterson indicated they are using rigid plate assumptions fo: calculating bolt loads.
g Review of the support redesigns at Millstone shows a considerable increase in basr plate thickness and anchor bolt sizes over the previous design. The original designs by Bergen - Paterson did not meet the current rigidity recuirements used by Stone & Webster.
Design deficiency reports by Long Island Lighting Company on Shoreham show that consideration of base plate flexibility has increased the pull-out loads on some bolts, and inspectio'n of the supports has shown that approximately 55 percent of the anchor bolts had incorrect embedment lengths.
Currently, I&E is considering whether Stone & Webster should be investigated for a Part 21 deviation and will be further investigating this matter.
- The Engineering Branch considers the problem at Millstone where several support plates were pulled out to be a ccmcination of base plate flexibility and anchor bolt design ::roblems. Since the anchor bolts were never tested for cyclic loacings, and the lines at Millstone experienced flow induced vibrations, the capability of the anchor bolts to withstand cyclic leadings should be addressed.
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",. K. Grimes D. G. Eisenhut -
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Based on the above information, the Engineering Branch recomends .
that this be considered a generic item for all operating plants, and a vendor inspection program be implemented with I&E to review the vendor derign procedures used for analyzing support base plates .
utilizing drilled anchor bolts along with the field insta111ation procedures utilized in installing the anchor bolts. Also, the load rating techniques used by the anchor bolt manufacturers for cyclic ,
loadings should be reviewed. The Engineering Branch has talked with I&E and consider the vendor inspection program to be the most efficient method of completing the necessary review. The Engineering '
Branch estimates approximately 15 man-weks will be required to review design procedures used by vendors and A/E fims. The '
Engineering Branch will set up a meeting with both AD's to determine the interface between the Engineering Branch and I&E required to implement the review.
The Engineering Branch is in the process of pnparing a feedback' memo to DSS on the base plate problem which is expected to be completed
'by June 9,1978.
gtisisisJs:6.EZ.i V. S. Noonan, Acting Branch Chief Engineering Branch Division of Operating Reac+4rs
~
ce: V. Stello, Jr. DOR W. Rutherford, IE U. Potopeus IE R. Mattson, DSS J. P. Knight, DSS R. Bosnak, DSS
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y '4 NUCLEAR REGULATORY COMMisslON 3
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4 MEMORANDUM FOR: R. J. Mat.tson, Director 11 4Y s, Division of Systems Safety
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FROM:
Victor Stello, Jr., Director c'p"g>J /
Division of Operating Reactors b y w s~ ]n
SUBJECT:
OPERATING EXPERIENCE MEMORANDUM NO. 13 PIPE SUPPORT BASE PLATE PROBLEM PROBLEM i
Recently during inservice inspections at Millstone Unit 1, structural failures of rigid pipe supports for class 2 safety equipment were observed. These inspections, recently implemented at Millstone, were conducted in accordance with Section XI of the ASME Code, as endorsed by regulation, 10 CFR 50.55 a(g), in February 1976.
Several base-plate anchor bolts of pipe supports in the Core Spray and the Low Pressure Coolant Injectior Systems at Millstone were not properly embedded; and, in some cases the anchor bolts were completely pulled out and no supporting function was provided.
Deficiency reports, in accordance with 10 CFR 50.55(e), filed by Long Island Lighting Ccepany, on Shoreham Unit 1, indicate that design of base plates with drilled anchor bolts using rigid plate assumptions has resulted in underestimation of loads on some anchor bolts. Inspection of anchor bolt installations at Shoreham has shown over fifty percent of the bolt installations were deficient. Supports for both piping systems and electrical raceways have been reported as deficient at Shoreham. ,
PRESUMED CAUSE .
It is currently believed that two interacting factors contribute to the failure of the supports. First, the design assumption that the base plates perform structurally as rigid instead of flexible members may provide icw estimates of imposed loads on the supports.
Secondly, incorrect anchor bolt embedment may also contribute to insufficient support.
The attached memorandum from V. Noonan to B. Grimes, dated June 2,1978, provices additional information.
o
. -{ t SAFETY SIGNIFICANCE Depending on equipment layout, improperly designed or installed anchor supports could: <
- l. re.sult in loss of support function in some cases; and,
- 2. result in high stressing of piping systems during a seismic event or during a significant flow transient.
REPAIR Millstone with assistance from Teledyne Engineering has completed e design modifications and repairs. These changes include increased base plate thickness and larger anchor bolts for failed supports ,
Shoreham in conjunction with Stone and Webster is evaluating both piping and electrical type supports. The review is scheduled to be complete'd by December, 1978.
00R ACTION The Engineering Branch will review the design procedures used on operating plants to determine anchor bolt loads, the techniques used to determine load ratings for anchor bolts, and the installation procedures.
This review will be done through an A/E vendor inspection audit in con,iunction with IE. These A/E audits will be started during early July, 1978.
We anticipate that criteria will be developed for design and installation of base plate-anchor bolt assemblies, and those operating plants requiring corrective action will be identified.
- Additionally EB staff will further assess the occurrence and .
corre'ctive actions taken at Millstone.
REC 05.E!!DATIONS ,
We recommend that this problem be addressed on all Cp and OL reviews.
At this time it appears that considerations should be given to the analytical methods used to.. determine whether or not base plates behave as f'.cxible or rigid members. This in turn may effect the ancher bolt sire and embedment to properly copa with loads imposed on the supports.
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It may be appropriate to require that applicants provide for review their: ,
- 1. methods for determining base plate thickness and anchor bolt loads;
- 2. criteria for anchor bolt installation; and,
- 3. criteria for load rating techniques for anchor bolts, including cyclic loads.
We shall coordinate our meetings, discussions and evaluations of this issue with your staff. Supplemental information will be provided.
,,,. ,, - *) s
' Vic' tor Stello, Jr., Director Division of Operating Reactors PRINCIPAL DOR PERSONNEL Reviewer: J. Fair l
Enclosure:
Memorandum dated 6/2/78 cc: w/ enclosure E. G. Case S. Hanauer -
R. S. Boyd H. R. Denton
. F. Schroeder -
DSS AD's DOR AD's
~
DOR BC's DOR SL's J. Fair
'-1'. Nichols W. Rutherford .
J. Sniezek
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