Letter Sequence Approval |
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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 OF AMERICA d
J "1 2 7 ec0* >C NUCLEAR REGULATORY COMMISSION
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a CIC:a of de Secrebry 2
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THE ATOMIC SAFETY AND LICENSING BOARD b
Marshall E. Miller, Esquire, Chairman;
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w, i up Dr. Kenneth A. McCollom, Member Dr. Hugh C. Paxton, Member
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In the Matter of
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PORTLAND GENERAL ELECTRIC COMPANY, et al. )
Docket No.50-344SP
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(Troj an Nuclear Plant)
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August 27, 1980 ORDER CLARIFYING INITIAL DECISION WITH REGARD TO CONTROL BUILDING MODIFICATIONS (August 27, 1980)
An Initial Decision was issued on July 11, 1980, in this proceeding regarding proposed modifications to the control building at the Troj an Nuclear Plant.
In that decision the Licensing Board found that nodifications proposed by the Licensee will be, adequate to bring the control. building into substantial compliance with Technical Specification 5.7.1, as required by the NRC's Order for Modification of License dated May 26, 1978.
The Initial Decision authorized performance of the modification work as proposed, and further provided that the modification program should be subj ect to a member of specified conditions [(a)-(v)].
The Initial Decision containa.d an Order which reads as follows :
" Control Buildine Modifications.
The Licensee is authorizec to anc shall proceec with modifications to the Control Building in order to restore substan-tially the originally intended design margins.
The modification program shall be accomplished in accordance Q$0h 8009020c %
$0/
. with PGE-1020,
' Report on Design Modifications for the Troj an Control Building', as revised through Revision No. 4, and as supplemented by PGE Exh. 27 (Licensee's Testimony ('.Broehl, et al.') on Matters Other Than Structural Adequacy of tee Modified Complex, March 17, 1980).
Any deviations or changes from the foregoing documents shall be accomplished in accordance with the pro-visions of 10 CFR part 50.59."
(Slip Opinion, pp. 56-57)
The Staff and the Licensee had recommended a somewhat similar provision in their proposed findings of fact and conclusions of law, which also purported to incorporate a number of other documents and letters, as follows:
" Control Buildine Modifications.
The Licensee is authorized to and shall proceed with modifications to the Control Building in order to restore substantially the originally. intended design margins.
The modifications program shall be accomplished in accordance with PGE-1020, ' Report on Design Modifications for the Troj an Control Building', as revised through Revision No. 4, and as supplemented by Licensee s letters dated February 28, March 28, June 22, June 29, July 5, 6 and 10, August 13, September 5 and 26, November 21, December 17, 21 and 2 2, 1979, and January 26, February 13 and 21, and March 5, 6,
17, 20, 21, an d 2 7, 1980; testimony filed by Licensee on March 17, 1980; Licensee's answers of Acril 2 and 14, 1980, to NRC Staff cuestions; and ' Licensee's Responses to Interrogatories dated August 27, 1979 from the State of Oregon' dated September 17, 1979 and suculemented February 29, 1980.
Any deviations or changes from the foregoing documents shall be accomplished in accordance with the provisions of 10 CFR Part 50.59."
(emphasis added) l
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Since the above-quoted provision in the Order did not contain the numerous letters and other documents described in the proposed findings, the Staff in its motion for clari-fication inquired whether the Board:
" intends solely to impose as licence conditions the provisions of PGE-1020 through Revision 4 and PGE Exh. 27, leaving all other material as part of the FSAR descriptions of the Control Building modification details, supporting analytical evaluations, acceptance criteria, Licensee commitments and implementing procedures which may not be changed without prior NRC approval pursuant to 10 CFR 550.59 in applicable instances?"
The answer to the above Staff inquiry is in the affirmative.
During the course of the evidentiary hearing the Licensing Board repeatedly informed the parties that it did not wish license conditions to incorporate by reference a large mass of documents,
sace of which were inconsistent with or were superseded by other documents.
It was felt that license conditions should be organized into one cohesive document, setting forth as precisely and clearly as possible the actual conditions to be imposed upon the Licensee.
For example, Dr. McCollom expressed concern that by the eLne all answers to interrogatories incorporated in the conditions were located and analyzed, there might be a lack of consistency.
He indicated that this ought to be resolved, particularly if the conditions were to be imposed in the license itself.
He also pointed out that the stack of materials included by reference in the conditions would be in the order of 10 to 12 inches thick, leading to confusion (Tr. 3469-70).
. Mr. Gray, NRC Staff Counsel, suggested that in testimony to be filed later they would la,y out precisely what the license conditions were.
In turn, Dr. McCollom suggested that the Licensee might want to provide a revised file in place of the accumulated interrogatories (Tr. 3502-03).
A discussion also occurred between Chairman Miller and Mr. Axelrad, Attorney for Licensee, about the fact that in Licensee Exhibit 25 some documents superseded other documents in the same exhibit.
Mr. Axelrad indicated that the latest information would have to be looked at and that the latest refinement in design would be reflected in the latest document.
Mr,. Axelrad also agreed that the earlier submittal then would stand without revealing the fact that it had been modified as such.
Chairman Miller, in turn, indicated that "The Board does not believe that we would like to have license conditions in the form or in any particular form where you would have to refer to other documents to see the present status."
He expressed the desire that the Board wished to have in one complete set, even though it be a lengthy document, the revised conditions so that they were set forth with finality (Tr. 3697-99, 3730-31).
Many of the materials rejected by the Board as license conditions incorporated by reference were contained in Licensee Exhibit 25, and were regarded as extraneous to license conditions.
Some examples are as follows:
a
. 1.
In Licensee's Exhibit 25-d, question 1, the answer is a safety related definition.
There is no indication of any condition that needs to be considered.
2.
In Licensee's Exhibit 25-d, question 5, the answer provides the basis for addition of future equipment.
The fact that there is an insignificant, or less than one percent addition for a 25 percent increase of the mass of the existing equipment, is a technicality, not a condition ner for construction.
3.
In Licensee Exhibit 25-d, question 20, the Licensee verifies that original FSAR pipe criteria are not impacted by the new analysis.
Again, this has nothing to do with conditions for construction.
4.
In Licensee Exhibit 25-e, question 11, there is a report of the examination of shrinkage which is merely an explanation rather than a condition required for the construction process.
3.
Zn Licensee Exhibit 25-e, question 19, there is an explanation of why higher allowables are appropriate in the STARDYNE model.
The explanation and answer is a part of the process, not a requirement or condition for construction.
~he above are a few examples of extraneous material found in the proposed conditions submitted by the Staff and Licensee, primarily on how the process was achieved rather than conditions for the construction process.
. Other documents in Licensee Exhibit 25 are responses which supersede other data or requirements previcusly stated.
Some examples are as follows:
1.
In Licensee Exhibit 25-q, attachment 10, there is described a supplemental response to question 6 which supersedes Licensee's previous response dated December 22, 1979, to that question.
The information in Licensee Exhibit 25-o has been replaced by Licensee Exhibit 25-q, thus causing ambiguity depending upon what part is referenced by parties involved.
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2.
In Licensee Exhibit 25-q, attachment 12, there are provided corrected response spectra to replace some pages of attachment 21-1, provided with Licensee ~'s response dated December 21, 1979, to NRC, question 21 dated October 2, 1979, and contained in Licensee Exhibit 25-o as well.
Again, there are ambiguities between different parto of Licensee Exhibit 25 in the recommended conditions by Licensee and Staff.
3.
In Licensee Exhibit 25-u, paragraph 3, the Licensee indicated that it had performed different analyses taking into account the postulated effects of gross bending, dead-load reductions, relative displacements between panels due to slipping, and elimination of resistance provided by beam-column connections.
Even with these additional conservatiscs, it concluded that the modified complex overall has an available capacity at least equar to that required to satisfy the 1.4 load factor, OBE criteria.
. Now there are two different calculations in the record, one of which is more conservative than the other and both of which are included in the conditions for the construction modifications.
4.
In Licensee Exhibit 25-g, question 6(a) the clear description of the bolt assembly and hardware arrangement indicated that the bolt assembly consists of a one and three quarter inch diameter rod threaded on both ends.
On the other hand, Mr. Broehl of Portland Gcneral Electric testified that the bolt assembly had how changed to consist of bolts of two inches diameter.
Here too there is an inconsistency between Licensee Exhibit 25 and the final modification arrangement (Tr. 3927).
In conclusion, the Staff has indicated in its motion that if the Board affirmatively answers the query set forth above (which it does), then the Staff will have the Licensee appropriately amend the FSAR to include the additional material.
It will also modify Technical Specification 5.7.2.1 accordingly.
The Licensee has stated that it understands that the supplemental documents are to be treated for regulatory purposes as the equivalent of the FSAR, mad that the Licensee considers itself bound to all the cocmitments it has made thereby.
The Licensee has correctly stated
W in its Response to NRC Staff's Motion for Clarification, its obligations under the license amendment issued pursuant to the
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Initial Decision.
IT IS SO ORDERED.
FOR THE ATOMIC SAFETY AND LICENSING BOARD
')L Japr. W Mdrshall E. Miller, Chairman Dated at Bethesda, Maryland this 27th day of August 1980.
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