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
[Table View] |
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DOCKETED 6
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UNITED STATES OF AMERICA E-SEP - 51980 NUCLEAR REGULATORY COMMISSION off;e, g g
%* t & Se:vice h
n 1.o Branch THE ATOMIC SAF M AND LICENSING BOA [b s
O m
9i Esquire, Chairman o
Marshall E. Miller,llom, Member Dr. Kenneth A. McCo Dr. Hugh C. Paxton, Member
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In the Matter of
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- O PORTLAND GENERAL ELECTRIC COMPANY, et al.
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Docket No.50-344SP
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(Troj an Nuclear Plant)
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(Control Building Proceeding)
J ORDER REGARDING MOTION BY STATE OF OREGON FOR RECONSIDERATION OF INITIAL DECISION
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(September 4, 1980)
By motion dated July 23, 1980, the State of Oregon sought reconsideration of the Initial Decision in this proceeding entered July 11, 1980.
The reconsideration concerns Oregon's request for certain accelerated reporting requirements, as contained in its proposed findings of fact and conclusions of law filed May 19, 1980.
The Appeal Board by its Order entered i
July 23, 1980, authorized the Licensing Board to act on the merits on Oregon's motion, notwithstanding the pendency on appeal of that party's exceptions to the Initial Decision.
The Licensee was authorized by Condition (1) to proceed with its control building modification program in accordance with the plans admitted into evidence (PGE-1020, as revised).
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The Order furtter provided that any " deviations or changes from the foregoing documents shall be accomplir*aed in accordance with 1-i the provisions of 10 CFR Part 50.59."
Section 50.59 provides in pertinent part that deviations and changes in the procedures as described in the safety analysis report, may be made by a licensee unless the proposed change involves an unreviewed safety question.
Reports on design changes or deviations show-ing no unreviewed safety questions would be submitted annually l
to NRC by the licensee, or at such shorter intervals as might be specified in the license.
In its proposed findings, Oregon proposed for the first time that the Licensee be required to comply with the reporting require-ments of Section 50.59 on an accelerated basis.
It proposed license conditions which would mandate submission of reports prior to the implementation of such changes, or in some instances within 14 days _of the decision to make such changes, rather than annually as otherwise provided.1/
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As the Staff noted in its response to Oregon's motion for reconsiderccion, there is no evidence of record in this proceeding which denstrates in any way that accelerated reporting of minor changes or deviations undertaken pursuant to Section 50.59 is 1/ State of Oregon's Proposed Findings of Fact and Conclusions of Law Concerning Design Modifications for the Trojan Control Building, dated May 19, 1980, pp. 2-5.
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l necessary.
In fact, what slight evidence there is on this matter indicates that accelerated reporting is not necessary.SI The 1
Licensee has also pointed out that the imposition of such a condition would be unnecessarily burdensome, especially in view l
of the large number of existing general and special reporting I
requirements.
There is nothing unique in the present situation which requires other than the periodic annual review by NRC to assure that no unreviewed safety questions are involved.3/
The Licensing Board in its Initial Decision did not impose Oregon's proposed license condition and did not explicitly set forth the reasons for rejecting it.
The Conclusions of Law did state that the Board "also considered all of the proposed l
findings of fact and conclusions of law submitted by the parties.
Those proposed findings not adopted in this Initial Decision are i
hereby rej ected" (Slip opinion, p. 54).
In view of the fact that Oregon had never presented an issue or suggestion of a contention as to accelerated reporting during extensive evidentiary hearings on both Phase I and S!NRC Staff's Response to Oregon's Motion for Reconsideration of The Initial Decision (August 15, 1930), p.4.
Tr. 4621-23 wherein Staff's witness Kenneth S. herring expressed the view that ainor deviations or changes from the proposed work sequence could be undertaken without the need for prior reporting or NRC review.
SILicensee's Response To The Proposed Findings of Fact and Conclusions of Law Filed By The NRC Staff And The State Of Oregon (May 29, 1980), pp. 7-9.
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> i Phase II proceedings, it is questionable whether an after-thought l
proposal for a license condition is covered by 10 CFR 2.760(c)(1).
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That section provides that the initial decision will include:
"(1) Findings, conclusions and rulings, with the reasons or basis for them, on all material issues of fact, law, or discre-tion presented on the record."
" Material issues" are not to be equated with issues never raised or discussed in many days of trial, nor revealed to the Board or j
parties until the final submission of proposed findings after the record has been closed.
Section 2.760(c) also provides that an initial decision "will be based on the whole record and supported by reliable, probative, and substantial evidence."
Here there was no evidence offered as to the necessity or reasonableness of accelerated reporting, although Oregon tendered written direct testimony and participated actively in cross-examination of witnesses.
Argumentative and conclusory proposed findings are no substitute for reliable and substantial evidence.
The Board therefore j
rejects Oregon's proposed license condition regarding accelerated reporting.
It is not clear whether Oregon is raising a second issue in its motion for reconsideration.
In its proposed findings dated >by 19, 1980, it also sought the following license condition:
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"(2) Add the following statements to Licensee's i
proposed license cc.tdition (1)(q) af ter the
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l sentence 'Any changes to piping systems necessary to ensure that the condition is l
met shall be performed before the structural 3
modifications are made. ' :
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'The evaluations to determine whether such changes are required shall be submitted to the NRC Office of Nuclear Reactor Regulation for information l
prior to impicmentation. '"
The Staff does not even discuss this second issue in its response to Oregon's motion for reconsideration.
The motion appears only to refer to accelerated reporting of design changes.
In any event, as the Licensee pointed out in its response, by the time the evidentiary hearing was held the Licensee had
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already performed the evaluations to identify the piping systems, i
equipment and components which had to be changed prior to the structural modifications in order to maintain their seismic qualification.
There has been no showing by Oregon of any reason now to submit such evaluations for work already done to the NRC Staff (Licensee's Response, pp. 9-11).
For the foregoing reasons, the Licensing Board adheres to its rejection of Oregon's proposed license conditions.
IT IS SO ORDERED.
FOR TE ATOMIC SAFETf AND LICENSING BOARD kCh./ w/f E-u05:n Marshall E. Miller, Chairman i
Dated at Bethesda, Maryland I
this Leh day of Septenber 1930.
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