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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' A ( h ci+ g h 7 UNITED STATES OF AMERICA 17 !
NUCLEAR REGULATORY COMMISSION 3 W{Wc BEFORE THE ATOMIC SAFETY AND LICENSING BOARD' In the Matter of
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PORTLAND GENERAL ELECTRIC
)
Docket No. 50-344 COMPANY, et al.
)
(Control Building)
)
(Trojan Nuclear Plant)
)
MEMORANDUM OF POINTS AND AUTHORITIES IN SUPPORT OF THE STATE OF OREGON'S PROPOSED FINDINGS OF FACT AND CONCLUSIONS OF LAW As is readily apparent fror stu: proposed Findings of Fact and Conclusions of Law, Oregon believes that the issues before the Board in this proceeding now appear to have been generally resolved.
Oregon retains, however, concerns as to the engineering analysis that remains to be completed by the Licensee, particularly as to seismic qualification of safety related equipment and as to engineering safety evaluations which may be performed by the Licensee prior to making any
?
changes in or deviations from the proposed modifications to
, the Trojan complex.
Such evaluations may be performed pursuant to 10 CFR 50.59 relating to Licensee's proposed condition. (1) (changes and deviations from PGE 1020 and representations made by the Licensee in certain other documents); pursuant to Licensee's proposed condition (2)(a)
(Trojan Operating License, appendix A, paragraph S.7.2.2, which requires NRC approval of design changes which cause a net 1% reduction in seismic capability, etc.); and pursuunt s
1 - MEMORANDUM OF POINTS AND AUTHORITIES i
80060s o tT9f9I
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i 1
to Licensee's proposed condition (1)(q) (changes in seismic qualification of safety related equipment).
j As set forth in Oregon's Proposed Findings 288 and 289, the great difficulty and complexity of the engineering i
design safety analysis necessary in order to design and review the proposed modifications has been apparent through-out the two-year course of this proceeding.
The " state of the art" level of the analysis has led to differences in engineering judgment between the Licensee and the Staff.
)
As to the analyses that have been completed, these dif-ferences have been resolved.
Nonetheless, Oregon believes that it is appropriate for the NRC staff to be kept informed in a timely manner of each of the engineering safety anal-yses that, as set forth above, will or may be done in the future.
Oregon does not believe that an NRC construction inspector or the NRC Regional Office of Inspection and Enforcement would have the expertise to perform a review of the complexity *,ssc iated with the seismic cafety questions that have been the subject of this proceeding.
For that reason, Oregon has proposed an accelerated reporting re-quirement as provided by 10 CFR 50.59 which states:
"(b) The Licensee shall maintain records of changes in the facility and of changes in the procedures made pursuant to this section, to the extent that such changes constitute changes in the facility as described in the Safety Analysis Report or constitute changes in procedures as described in the Safety Analysis Report.
These records shall include a written safety evaluation which provides the bases for the 2 - MEMORANDUM OF POINTS AND AUTHORITIES
j
.l determination that the change, test, or experi-ment does not involve an unreviewed safety question.
The Licensee shall furnish to the appropriate NRC regional office shown in appendix D of Part 20 of this chapter with a copy to the Director of Inspection Enforcement, U.S. Nuclear kegulatory Commission, Washington, DC 20555, annually or at such shorter intervals as may be specified in the license, a report containing a brief description of such changes, tests and experiments, including a summary of the safety evaluation of each.
(Emphasis added.)
l The burden on the Licensee of e.ccelerated reporting i
to the NRC Staff is simply a matter of transmitting material and reports (that are otherwise required to be prepared) to the NRC according to the schedule proposed in Oregon's modification of Licensee's proposed condition (1) and (1)(q) rather than waiting to submit the same material in an annual report.
An annual report would be of no practical use during the modification work as the work will have been completed and " set in concrete" long before reports of changes in the modifications reached the appropriate staff.
It is important to note that Oregon has not suggested that the Staff approve in advance each change or deviation in the modifications.
Oregon believes that with timely receipt of the Licensee's engineering safety analysis reports, the appropriate NRC Staff experts can provide meaningful review of Licensee's analyses and that adequate enforcement power exists.
In order to aid in making the Staff's review timely, Oregon has suggested in proposed condition (1) that copies 3 - MEMORANDUM OF POINTS AND AUTHORITIES
be sent directly by the Licensee to the Office of Nuclear Reactor Regulation as well as to the NRC Region V Office of Inspection and Enforcement.
The findings and conditions proposed by Oregon are
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intended to increase the likelihood that the modifications to the complex in all their final details will meet the seismic safety standards that have been the concern of all the parties to this proceeding.
Oregon's proposals are within the provisions of the appropriate NRC regulation, 10 CFR 50.59(b), supra, and do not create an undue burden on the Licensee.
For all of the above reasons, they should be adopted by the Board.
Respectfully submitted, bl
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FRANK W. OSTRANDER, JR.i Assistant Attorney Gendrall Of Attorneys for the Ordgon Department of Energy 4 - MEMORANDUM OF POINTS AND AUTHORITIES
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CERTIFICATE OF SERVICE I, Frank W. Ostrander, Jr. hereby certify that on this 19th day of May, 1980, I served the within " Memorandum of Points and Authorities in Support of the State of Oregon's Proposed Findings of Fact and Conclusions of Law" upon the following parties of record by then depositing in the United States mail at Portland, Oregon, full, true, and correct copies thereof, addressed to the said parties of record at the following addresses listed below, and prepaying the postage thereon:
i Marshall E. Miller, Esq., Chair.
Mr. David B. McCoy Atomic Safety and Licensing Board 348 Hussey Lane U.S. Nuclear Regulatory Comm'n Grants Pass, OR 97256 Washington, DC 20555 Ms. C. Gail Parson Dr. Kenneth A. McCollom, Dean 800 S.W. Green #6 Division of Engineering, Portland, OR 97205 Architecture & Technology Oklahoma State University Ronald W. Johnson, Esq.
Stillwater, OK 74074 Corporate Attorney Portland General Electric Dr. Hugh Paxton 121 S.W. Salmon Stree't 1229-41st Street Portland, OR 97204 Los Alamos, New Mexico 97544 William %
Kinsey Mr. John A.
Kullberg 1002 N.E.
Holladay 15523 S.E.
River Forest Dr.
Portland, OR 97232 Portland, OR 97222 Ms. Nina Bell Coltmbia Environmental Council 632 S.E.
18th 203 S. First Street Portland, OR 97214 St. Helens, OR 97051 Mr. Stephen M. Willingham Maurice Axelrad, Esq.
555 N. Tomahawk Drive Lowenstein, Newman, Reis, Portland, OR 97217 Axelrad & Toll Suite 1214 Mr. Eugene Rosolie 1025 Connecticut Avenue NW Coalition for Safe Power Washington, DC 20036 215 S.E.
9th Avenue Portland, OR 97214 1/ CERTIFICATE OF SERVICE
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Dr. Reed Johnson Atomic Safety and Licensing Office of the Executive Legal Appeal Board Director U.S.
Nuclear Regulatory Comm'n U.S.
Nuclear Regulatory Comm'-
Washington DC, 20555 Washington, DC 20555 Joseph R. Gray Docketing and Services Sectio.
Counsel for NRC Staff Office of the Secretary U.S. Nuclear Regulatory Comm'n U.S.
Nuclear Regulatory Comm':
Washington, DC 20555' Washington, DC 20555 Alan S.
Rosenthal, Esq.
Atomic Safety and Licensing Atomic Safety and Licensing Appeal Board Appeal Board U.S. Nuclear Regulatory Comm':
U.S. Nuclear Regulatory Comm'n Washingon, DC 20555 Washington, DC 20555 Dr. John Buck Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Comm'n Washington, DC 20555 e
u f
FRANK W. OSTRANDER, JR.
Assistant Attorney General l
O 2/ CERTIFICATE OF SERVICE