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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UNITED. STATES yg p,
NUCLEAR REGULATORY COMMISSION 5 (?,,z
- *E WASHINGTON, D. C. 20555 o.
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May 30, 1980 Marshall E. Miller, Esq., Chainnan Dr. Kenneth A. McCollom, Dean Atomic Safety and Licensing Board Division of Engineering, U.S. Nuclear Regulatory Coninission Architecture & Technology Washington, D.C.
20555 Oklahoma State University Stillwater, Oklahoma 74074 Dr. 5 Jgh C. Paxton 1223 41st Street Los Alamos, New Mexico 87544 In the Matter of Portland General Electric Company, et al.
(Trojan Nuclear Plant)
Docket No. 50-344 (Control Building)
Gentlemen:
In the course of its review of the "NRC Staff's Proposed Finding's of Fact and Conclusions of Law on Modification to the Trojan Control Building" (Staff's Proposed Findings), filed on May 19, 1980, the Licensee discovered and brought to the Staff's attention a possible error and lack of clarity in a portion of the Staff's Proposed Findings. Specifically, the matter in question is footnote 34 on page 134 of the Staff's Proposed Findings which states:
i An additional concern with regard to displacements arises from the fact that, under certain conditions, Control J
Building displacement is necessary to develop the capa-cities required to resist the factored OBE (Staff Exh. 17A, l
pp. 28-29, As. 19H, 191). There is one elevation at the interface between the Control and Turbine Buildings where the clearance will not be changed by the proposed modifi-cations but where that clearance will only accommoda'te a factor of 9.52 times the STARDYNE calculated Control Building displacements.
However, the factor of 9.52 provides ample margin so that even with a factor of 9.52 times the STARDYNE displacements (and additional factors to account ft.r the factored OBE and uncertainties resulting in a total factor of 7.5), the necessary displacements to develop,the required capacity can take place without building contact (Staff Exh. 17A, pp. 28-29, As. 19H, 191; PGE Exh. 33, A.21; Tr. 4618-19 (Herring)).
(emphasis added) h 8006030I
- 2.-
o The Licensee pointed out that the " total factor" of 7.5 in the underlined portion of footnote 34 is not identified in the record.
From the Staff's review of the record and the derivation of the " total factor," it has become clear that the " total factor" of 7.5 set forth in footnote 34 is in error and also that, while the " total factor" may be derived from evidence in the record, that " total factor" itself is not presented on the record.
Accordingly, the Staff herewith submits a correction to its proposed findings in the fonn of a corrected footnote 34 as set forth below. This revised footnote changes the " total factor,"
correcting it from 7.5 to 8.86, and explains its derivation from evidence on the record (note that a licensing board may draw conclusions by applying known engineering principles to, and making mathematical calcu-lations from, facts in the record whether or not any witness purported to attempt this exericse.
Vermont Yankee Nuclear Power Corp. (VermontYankee Nuclear Power Station), ALAB-229, 8 AEC 425, 437, rev. on other grds.,
CLI-74-40, 8 AEC 809 (1974)).
Footnote 34 on page 134 of the Staff's proposed findings filed on May 19, 1980 should be replaced with the following corrected footnote 34:
34/ An additional concern with regard to displacements arises from the fact that, under certain conditions, Control Build-ing displacement is necessary to develop the capacities required to resist the factored OBE (Staff Exh. 17A, pp. 28-29, As. 19H, 19I).
There is one elevation at the interface between the Control and Turbine Buildings where the clearance will not be changed by the proposed modifications but where that clearance will only accommodate a factor of 9.52 times the STARDYNE elastically-calculated Control Building displace-ments (PGE Exh. 33, A.21, p. 1 of 2; Staff Exh. 17A, p. 29, A.19I).
The Turbine Building displacement at this point is 2.4 inches and the available gap between the Control and Turbine Buildings is 3.0 inches (Tr. 4618 (Herring)).
This leaves a reduced gap into which the Control Building can deflect of 3.0 - 2.4 or 0.6 inches. Since this space can accommodate 9.52 times the STARDYNE calculated displace-ment for the Control Building (PGE Exh. 33, A.21, p. 1 of 2; Staff Exh. 17A, p. 29, A.191), such STARDYNE calculated displacement at this point is 0.6
= 0.063 inches.
9.52 The actual Complex displacement at this point (in contrast to the STARDYNE elastically-calculated displacement) under factored OBE conditions and accounting for uncertainties and stiffness degradation is 0.41 inches (Tr. 4618 (Herring)).
Combining this with the Turbine Building displacement of 2.4 inches gives a combined displacement for the Control and Turbine Buildings for a factored OBE of 2.81 inches.
Under Technical Specification 5.7.2.2(c) (PGE Exh. 33, Atth. 21-1), which will be imposed as a condition of the modifications (see paragraph 263 infra), changes to the
facility after completion of the Control Building moditi-cations will be limited such that no more than a 5% increase in combined interstructure displacements between the Control and Turbine Buildings will occur. This could result in an increase in combined Control and Turbine Buildings displace-ments of 0.05 x 2.81 = 0.14 inches. Since, under Technical Specification 5.7.2.2, all of this could be displacement of the Complex, total Complex displacement at the point of minimum clearance could increase to 0.41 + 0.14 = 0.55 inches.
In addition, Technical Specification 5.7.2.2 will allow an increase in equipment weight, which is 3% of the weight of the Complex (Tr. 4619 (Herring)), of 10% (PGE Exh. 33, Atth.
21-1), resulting in an increase in Complex displacement of 0.10 x 0.03 x 0.55 or about 0.002 inches.
The Complex displacement of 0.552 inches (0.55 inches plus 0.002 inches) could be further increased by 1% to 1.01 x 0.552 or about 0.558 inches since Technical Specification 5.7.2.2(a) and (b) allow a 1% increase in lateral shear forces in the modified Complex or a 1% decrease in the lateral resistance of the modified Complex (PGE Exh. 33, Atth. 21-1).
Thus, the maximum Complex displacement for the factored OBE, accounting for stiffness degradation, uncertainties, and changes to the modified Complex permitted by Technical Specification 5.7.2.2., is 0.558 inches.
This actual ultimate displacement is a factor of 0.558 = 8.86 0.063 times the STARDYNE elastically-calculated displacements at this point.
Since a factor of 9.52 times the STARDYNE calcu-lated displacement is available (Staff Exh.17A, p. 29, A.19I),
the necessary displacement of the Complex to develop the required capacity can take place without building contact.
(Staff Exh. 17A, pp. 28-29, As. 19H, 19I; PGE Exh. 33, A.21,
- p. 1 of 2).
The Staff respectfully requests that its Proposed Findings be considered corrected in accordance with the above.
Sincerely, f
.t.o J sep R.Graf ou 'el for NRC St ff cc: Service List e
t-
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