Letter Sequence Other |
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|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement
Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: 05000344/LER-1978-020, Forwards LER 78-020/03X-3, 05000344/LER-1978-020-03, /03L-0:on 780622,during Design Review for Piping Stress at Wall Penetrations,One Sys Was Found to Have Stress Exceeding Allowable Code.Caused by Design Error.Grouting Around Pipe Removed & Stress Reduced, ML19207C007, ML19209A322, ML19209A323, ML19209A336, ML19209A363, ML19209A432, ML19209A435, ML19209B063, ML19209B180, ML19209B241, ML19209D051, ML19209D056, ML19225A294, ML19241A963, ML19241A969, ML19241C194, ML19242B129, ML19242B972, ML19247B146, ML19248C628, ML19248C934, ML19249D678, ML19250C450, ML19253C727, ML19254D131, ML19254F178, ML19256F544, ML19256F546, ML19256F990, ML19256F993, ML19260C591, ML19261A687, ML19261D547, ML19261D820, ML19263E970, ML19267A290, ML19267A296, ML19269D190, ML19270E836, ML19270G402, ML19270H454, ML19271A997, ML19275A272, ML19282A785, ML19289C608, ML19289F192, ML19290C976, ML19294B198... further results
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MONTHYEARML19209A3631974-02-25025 February 1974 Burn Tests on Silastic Rubber-Coated Glass Drop Cloths. Prof Qualifications of Ew Edwards Encl Project stage: Other ML19256F5461974-06-30030 June 1974 Miscellaneous Paper C-74-12,Pullout Resistance of Reinforcing Bars Embedded in Hardened Concrete, Prepared by Engineer Waterways Experiment Station Project stage: Other ML20195C3451978-04-28028 April 1978 Informs That Structure of Walls in Control Bldg Does Not Meet Seismic Criteria for Sar.Reanalysis Confirms Control Bldg Will Maintain Structural Integrity & Plant Will Retain Functional Capability Under Design Loads Project stage: Other ML20195C3641978-05-26026 May 1978 Clarifies Items 2 & 3 of DG Eisenhut 780502 Memo Re Proposed Mod to Plant Spent Fuel Storage Rack Proceedings.Design Engineer Activities in Fuel Bldg Design Should Be Considered Supporting Role Project stage: Other ML18004B9711978-06-0202 June 1978 Addresses Pipe Support Base Plate Problem.Discusses Review of Support Redesigns & Capability of Anchor Bolts to Withstand Cyclic Loadings Project stage: Approval ML20195C3511978-06-29029 June 1978 Forwards Affidavits of CM Trammell & LC Shao Re Safety Significance of Control Bldg Design Deficiencies & NRC Findings Concerning Significant Hazards Considerations Project stage: Other ML20195C3851978-06-29029 June 1978 Affidavit of Chales M. Trammel,Iii.* Staff Concluded That an Amendment Authorizing Operation of Trojan Nuclear Power Plant Pending Upgrading of Seismic Capability of Control Bldg Walls Would Constitute a Decrease in Safety Margin Project stage: Other ML20195C4001978-06-29029 June 1978 Affidavit of LC Shao Re Control Bldg Design Errors Resulting in Substantially Weaker Walls than Intended by Original Design criteria.As-built Structure Has one-half of Seismic Capacity & Safety Margin Project stage: Other ML20195C3741978-06-30030 June 1978 Forwards Proposed Schedule of Actions to Bring Plant Control Bldg Into Substantial Compliance Ww/Requirements & Intended Design Margins.Detailed Description of Actions,Design Changes & Mods Will Be Submitted Prior to 780901.W/o Encl Project stage: Other 05000344/LER-1978-020-03, /03L-0:on 780622,during Design Review for Piping Stress at Wall Penetrations,One Sys Was Found to Have Stress Exceeding Allowable Code.Caused by Design Error.Grouting Around Pipe Removed & Stress Reduced1978-07-21021 July 1978 /03L-0:on 780622,during Design Review for Piping Stress at Wall Penetrations,One Sys Was Found to Have Stress Exceeding Allowable Code.Caused by Design Error.Grouting Around Pipe Removed & Stress Reduced Project stage: Other ML20195C4581978-08-19019 August 1978 Forwards NRC Questions & Licensee Responses,780804-17 Based on Info Provided by Bechtel Re Control Bldg.All Walls Except 1B,2 & 3 Have Dowel Capacities Exceeding Shear Capacities Controlled by Either Shear or Bending Project stage: Other ML20195C4621978-08-21021 August 1978 Forwards Final NRC Responses to Questions 6 & 10 Re Control Bldg Mods,Based on Info Provided by Bechtel.Equipment in Structure Should Continue to Be Capable of Resisting Seismic Loadings Resulting from Real Earthquakes Project stage: Other ML20195C5331978-08-22022 August 1978 Responds to Re Amendment Permitting Temporary Operation of Plant Independent of Public Hearing.Law Requires Hearing to Be Held in Connection W/Amend to OL Project stage: Other ML20150A6081978-08-30030 August 1978 Forwards Request for Addl Info Re Control Bldg Per Seismic Nonconformance Project stage: RAI ML20150A6141978-09-0101 September 1978 Forwards Preliminary Results of Stardyne Finite Element Analysis of Trojan Control-Auxiliary-Fuel Bldg Complex & Assessment of Seismic Load Resistance of Bldg as Presented at 780828 Meeting. Lic. NPF-1 Project stage: Meeting ML20195C1431978-09-0707 September 1978 Responds to Commissioner Davis Addressed to Commissioner Bradford & Expressing Concerns Re non-conformance to Specs of Control Bldg at Plant & Effect of Facility Shutdown on Rate Payers Project stage: Other ML20147C2411978-09-12012 September 1978 Forwards Corrected Supplementary Info Transmitted by Ltr Project stage: Supplement ML20150A6441978-09-20020 September 1978 Forwards Final Results of Rev & Evaluation of Recent Stardyne Finite Element Analysis for Existing Control Bldg of Subj Facil.Suppl Structural Evaluation Response to Specified SSE Event,& Response to Questions Encl Project stage: Other ML20150A6651978-09-20020 September 1978 Responds to Specified SSE Event.Stardyne Dynamic Analysis Was Used to Determine Structural Capacities & Forces. Concludes That Control Bldg Can Withstand SSE Event Safely Project stage: Other ML20150A6581978-09-21021 September 1978 Order Re Responses to NRC Interrogatories by Coalition for Safe Pwr & Consolidation.Cfsp Must:Respond W/In 14 Days to S1,S2,E1,G1,G2,G3,G8 & All Other Interrogatories;Clarify the Status of Spokesmen.Motion for Reconsideration Is Denied Project stage: Approval ML20062B9611978-09-28028 September 1978 Forwards 780628 Memo to R Mattson Re Info on Failures of safety-related Pipe Supports at Millstone 1 & Design Deficiencies on Similar Equipment at Shoreham.Aslb Notified of Pipe Support Base Plate Design Project stage: Approval ML20062A5471978-09-29029 September 1978 Notifies That Staff Is Unable to File Testimony on Interim Oper of Subj Facil Before 781013 Re Finite Element Analysis. Urges That ASLB Commence Hearing on 781018 or 781023 Project stage: Request ML20147E6401978-10-0303 October 1978 Transcript of SR Christensen Testimony Re Description of Seismic Instrumentation & Engineering Investigations to Be Conducted Following Earthquake Project stage: Other ML20147E6321978-10-0303 October 1978 Transcript of Dj Broehl Testimony Re Plant History, Chronology of Events Since Apr 1978 & Summary of Licensee Efforts to Ensure Safe Interim Operation of Control Bldg Project stage: Other ML20148A0601978-10-0606 October 1978 Direct Testimony of Harold Laursen Re Assignment to Eval Ability of Subj Facil Bldg Shear Walls to Resist Seismic Loading.Determined Shear Walls Can Withstand .25g Safe Shutdown Earthquake Project stage: Other ML20062C1421978-10-11011 October 1978 Notice of Evidentiary Hearing on Issue of Interim Operation & Limited Appearance.Hearing to Determine Whether Interim Operation Should Be Permitted Prior to Mods Required by Order Will Be Held on 781023 & 1030-1101 Project stage: Other ML20148C0251978-10-13013 October 1978 Responds to NRC 781011-13 Questions Re Supplemental Structural Evaluation of Control Bldg,Particularly Shear Wall Capacity.Certificate of Svc Encl Project stage: Supplement ML20062B2751978-10-13013 October 1978 Forwards Ks Herring Testimony on Structural Adequacy of Trojan Control Bldg for Interim Operation & RT Dodds & Je Knight Testimony on Seismic Features Relevant to Facility Safety Project stage: Other ML20062B2791978-10-13013 October 1978 Testimony Verifying That Reasonable Assurance Exists That Shear Walls Will Withstand SSE or Obe.Original Intended Margins of Safety Reduced & Should Be Restored Project stage: Other ML20062B2821978-10-13013 October 1978 Testimony Describing Insp of Humboldt Bay Following 5.4 Richter Magnitude Earthquake on 750609 & Std Insp Procedures After Seismic Event.Procedures to Be Followed During Earthquake Detailed Project stage: Other ML20062B2861978-10-13013 October 1978 Testimony Responding to ASLB Questions Re Effects of Seismic Event on Plant Features Important to Maintaining Safety of Facility.Certificate of Svc Encl Project stage: Other ML20147F0961978-10-16016 October 1978 Licensees Testimony on Capability of Subj Facil to W/Stand Seismic Events.Statements of Qualifications,Ref & Append Are Attached.Description of Affected Structure & Deficiencies Such as Amount & Arrangement of Reinforcing Steel Provided Project stage: Other ML20147F0891978-10-16016 October 1978 Testimony of Bart Withers,As Superintendent of Subj Facil W/Statement of Qual Attached.Describes Capability of Plant to Function & Plant Staff to Respond Properly Immediately Following a Seismic Event Project stage: Other ML20062B4191978-10-16016 October 1978 Forwards Ks Herring Testimony Re Suppl to Stardyne Analysis & Effect on Structural Capacity of Control Bldg.Certificate of Svc Encl Project stage: Other IR 05000344/19780201978-10-16016 October 1978 IE Inspec Rept 50-344/78-20 on 780905-29 During Which No Items of Noncompliance Were Noted.Major Areas Inspec Incl: Plant Opers,Maint,Surveillance Test,Facil Security & Licensee Event Followup Project stage: Request ML20062B4251978-10-17017 October 1978 Testimony Re Suppl to Stardyne Analysis & Effect of Structural Capacity of Control Bldg.Structure Can Withstand SSE & Less Severe Obe,But Suppl Info Alters Earthquake Level Requiring Plant Insp Project stage: Other ML20062B9591978-10-19019 October 1978 Forwards Recent Memoranda Re Certain Problems Experienced in Connection W/Pipe Support Base Plate Design.Staff Determining If Problems Have Generic Implications for Operating Facilities.Aslb Will Be Kept Informed Project stage: Other ML20062C6271978-10-27027 October 1978 Forwards Further Response to NRC Staff Tech Questions Re Stardyne Analysis & Review.Includes Description of Criteria & Procedures Used & Explanation of Dev of New Acceleration time-history.Cert of Svc Encl Project stage: Other ML20062D3481978-11-0606 November 1978 Cross-examination or Testimony Re Analysis & Review by Licensee Poge of safety-related Matls in Control-Auxiliary- Fuel Bldg Complex Will Be Taken at 781211 Hearing.Nrc Given Time to Reply to Interrogs.Proposed Findings Due 781120 Project stage: Other ML20197D4801978-11-22022 November 1978 Forwards Suppl Documentation in Support of Floor Response Spectra Provided in 781027 & 781102 Responses to NRC Info Requests.W/Cert of Svc Encl Project stage: Other ML20197D4691978-11-22022 November 1978 Forwards Suppl Document Supporting Floor Response Spectra Provided in 781027 & 781102 Submittals to NRC in Response to Request for Additional Info Project stage: Request ML19305A0701978-12-11011 December 1978 Limited Appearance Statement by Rd Pollard of Ucs to Explain the Kind of Inquiry Possible,Yet Untapped,W/Respect to Any Person of Pollards Competence & Commitment in Field of Nuclear Plant Licensing Project stage: Other ML19305A0631978-12-18018 December 1978 Forwards Limited Appearance Statement by Rd Pollard of Ucs. W/Encls Project stage: Other ML19270E8361978-12-21021 December 1978 Partial Initial Decision Re Whether Operation of Facility Should Be Permitted in Spite of Identified Design Deficiencies in Control Bldg & Prior to Mod.Decision Is to Allow Interim Operation Project stage: Other ML19267A2901978-12-22022 December 1978 Forwards Partial Initial Decision,Amend 35 to License NPF-1 & Notice of Issuance Project stage: Other ML19267A2961978-12-22022 December 1978 Amend 35 to License NPF-1.Modifies Waiver Portions of Tech Specs & FSAR Criteria Which Have Not Been Followed Due to Design Deficiency in Control Bldg Shear Walls Project stage: Other ML19267A3021978-12-22022 December 1978 Notice of Issuance of Amend 35 License NPF-1 Project stage: Approval 05000344/LER-1978-020, Forwards LER 78-020/03X-31978-12-26026 December 1978 Forwards LER 78-020/03X-3 Project stage: Other ML19308A2121978-12-26026 December 1978 Reportable Occurrence on 780622: Piping Penetrations Not Designed to Be Solidly Grouted Were Found to Be Solidly Grounted.During Subsequent Design Review,Excessive Support or Pipe Stresses Found on 11 Isometrics. Probable DELETE-RO Project stage: Other ML20150F0221979-01-0303 January 1979 FOIA Request for 20 Documents Listed Re ECCS Performance Calculations & Calculational Errors Identified by Westinghouse & Portland GE, & on Pipe Cracks in Containment Vessel of Trojan Plant Project stage: Request 1978-04-28
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Text
MRE ogf8 137:
unnD srxmS OF asatcA g g[9 g
NUCURR REGExIDKY OCMESSICH t
In the Matter of
)
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)
N PORIIAND GENERAL ELECIRIC C3fANY, et al. )
Docket No. 50-344
- DL'
)
(Trojan Nuclear Plant)
)
(Control MMS)
ORDER EStAMTWTNG Ft.Vibt.u SCHEDGE (July 26,1979)
The following schedule is hereby adopted by the Licensing Board to govern the course of Phase II of this proceeding:
September 7, 1979 SER issued by Staff.
September 21, 1979 Written testinony Med.
Last date for filing discovery requests on Staff's EER.
October 10, 1979 Evidentiary hearing cc::mences.
It is so ordered.
FDR THE AIOMIC SAFE 1Y KO LICENSING BOARD LThkA.a/
f/
Marshall E. Miller, Esq. chm"9m Dated at Bethesda, Maryland this 26th day of July 1979.
1027 204 790gg50ggg
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UNITED STATES 3
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NUCLEAR REGULATORY COMMISSION
-T '.
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS I
5.Y(
WASHINGTON, D. C. 20555
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July 16,1979
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Honorable Josep. M. Hendrie cTM*M Chairman U. S. Nuclear Regulatory Com:nission g
Washington, DC 20555 Y
M EAII.LY GDEATING STATION, NUCLEAR 1 SI3 ECT:
Dear Dr. Hendrie:
12-14, 1979, the Advisory Committee on curing its 231st meeting, July Safeguards reviewed the design of the pile foundations for the Sailly Generating Station, Nuclear 1, being construered by the Northern Ree:to Indiana Public Service Cocpany (NIPSCO).
i AC.:.5 Subce=it:ee at a meeting held in Portage, Indiana f
The co=ittee also had the benefit of the documen July 9,1979 statements received from r, embers of the public.
- n your letter dated June 8,1979, you made the f:ilowing rec.uest:
"The Co-.ission re:uests the Co=ittee to identify and address de significance (if any) of the engineering and safe:; issues arising from use of the shorter pilings as i.e lenger pilings.
In particular:
( '. ) is ep: sed ::
e use of shorter pilings a significant design change from the standpoint of engineering, and would it recuire significant alteration of other aspects of the design of
- e facility; (2) what differences, if any, would there be ir. the safety of the facilitv. dec.endinc on whether
' anger or sh:::e pilings are used?"
driving T.e ',=ittee heard rep :ts on the experience to date relating to the 2e site, including the exploratory driving of the
- f pi._s a:
i and pile t.e inter edded sand and clay layer, and the various b:r ngsOne Cor.ittee aisc
.he till ::
have been made ever the past fe. years.
.n::
be provided ring to the fac ::s Of safety ::
f the
- ad :ss.5..a:
analyses re.
earieus leading combina:icns and to the expe::ed sa:tle ents o
.e a rd r e:c r s 0.-
ag ains:
3.ru::.::e5 s.:pp ::ed on piles.
1027 205 Does TO&/Sco63
~
5:norable Joseph F.. Hendrie July 16,1979 100ROR'8lM
~
"he Coc::tittee has identified only two potential safety iss:.ues arising from the use of the shorter piles as opposed to the longer pilets, and has con-cluded that neither of these will have any effect on the ssafety of the facility if the procedures proposed by NIPSCO or required iby the AC StaEf are followed.
Tne first of these results from the fact that some of the sexploratory longer piles were installed with the aid of high pressure water fiets which resulted in disturbance.of the soil (chiefly the sand) in the inter: bedded layer.
'Ihis disturbance is li=ited to only a snall portion of the founddation area at four locations.
Unless renedial measures are taken, the shorte r piles driven in these areas might be deficient in load-bearing capacity.
N!?5CO has preposed the use of " compaction piles" in the a reas of di'sturbed soil to densify the disturbed soil so that it will be able to provide su:por: ecuivalen to that in the other areas.
Tne NRC Staff believes that this procedure is acceptable, and the Cecaittee agrees, sutoject to compliance
rh the following procedures:
1.
Exploratien by borings or by penetration devices t:0 dete=ine the vertical and horizontal extent of ths2 disturbed areas.
2.
Compaction of the disturbed material by driving compaction piles.
3.
Verification b'y borings or by penetration devi'ces that all cf the disturbed soil has been compacted.
Derf min; a compression load test on at least one prod.:::icn pi.e i each disturbed area to verify i:ts lead-carrying capacity and load-deformation chara --
teristics.
N ?SCO has agreed to these procedures.
'~ne second issue resulting from the use of the shorter pil(es is the potential settlement of the supported structures.
':he settlement af ter construction weald have been expected to be essentially zero for the lo:nger pile foundation.
F: the shorter piles, the settlement has been estimated by NIPSCO to be on the order of wo inches.
Set:J.ecent of this.agnitude is not unusual for a
..:: lear c'a.: a.d
- Cd have no significance to safe:y.
CJhe Cc==ittee has re: r. ended ::..s S ' Staf f, however, that the method of calculatinc the se :le en: be revie ed :: assure -hat it has een done cc..servativel.
1027 206 J
Honorable Joseph M. Hendrie July 16,1979 In addition, NIPSCO has proposed a program to measure settlenent-at numerous locations on the structures during operation of the plant, and t he NRC Staff has stated that such measurements will be required by the Technical Specifi-cations and that suitably conservative limits on permissible setT_lenents will be established.
In view of these commitments, the Committee bel.:ieves that potential settlements, even if greater than those now predicted,. would not represent a hazard to the public.
The NRC Staff is cont nuing its review of the foundation design, and the i
Cormittee believes that the remaining foundation-related issues, not related to the use of shorte. piles, can be resolved by the Staff.
In direct respense to the cuestions raised by your recuest, the AGS be.11 eves that:
1.
The use of shorter piling is not a significant design chztnge frot the standpaint of engineering.
2.
De use of shorter pilirs.rauld not recuire significant alteration of cther aspects of the design cf the facilit,j.
3.
Bere will be no difference in the safety of the facility depending en wtether longer or shorter pilings are used d.f the matters referred to above are treated as now progese:5.
Sincerely, Max W. Carbon Chairman Referen:es:
1.
Preliminary Safety Analysis Report on Bailly Generatin: Stat.i cn, Nuclear 1.
2.
Cesign Analysis and Installation of Driven H-Piles Foundation, Rep =rt SL-3629, set.itted cn March *, 1978.
3.
N;P500's Responses to lac Staff Questions, subcittM on Ju'y-14, 1978.
4.
Indicator ?ile Program, subnitted by NIPSCO to NRC on Septec ber 26, 1978.
5.
Supplementary Information on Driven H-Pile Foundation, NIPSCO, December 4, 1973.
6.
Le :er, C. 5.
Jassa;' c, NRC, to H. P. Lyle, N:?500, June 25, 1979.
Saill; Generating 5:a;ien, Nuclear 1 Construe:i:- Permit, '*a;- ;, 1_:74.
5.
- epes: b,. :he ?:::er County Chap;er of the ::aa>..;;'.::n Leag ue of America, I..:., Fe'; r:Iri 2~, 1979.
9.
Ls :er, I. ". 5he rb, N;PSCO, Oc O. 3. Vassall, NRC, J..le 25, 1979.
1027 207