Letter Sequence Other |
|---|
|
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 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 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 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 ML19267A3021978-12-22022 December 1978 Notice of Issuance of Amend 35 License NPF-1 Project stage: Approval 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 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] |
Text
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
PORTLAND GENERAL ELECTRIC COMPANY,)
Docke t No. 50-344 et al.
)
(Control Building
)
Proceeding)
(Trojan Nuclear Plant)
)
)
AFFIDAVIT OF BART D.
WITHERS COALITION FOR SAFE POWER'S CONTENTION NO. 17 AND CONSOLIDATED INTERVENOR'S CONTENTION NO. 2D 1.
My name is Bart D.
Withers.
I am employed by P 7rt-land General Electric Company (PGE) as General Manager of the Trojan Plant.
I have been employed in this position since January 1, 1977.
My professional qualifications are contained in an attachment to this affidavit.
This affidavit was pre-pared by me or under my supervision.
2.
I was assigned as Trojan Nuclear Plant General Manager at the time the deficiency with the Control Building walls was identified.
I participated in many of the meetings between PGE and Bechtel Power Corporation (Bechtel) concerning the capabilities of the building in its as-built condition and the effects of any proposed building modifications on the plant operational capabilities.
As a member of the Plant Re-view Board and Nuclear Operations Board, I participated in the review of the plant modifications, procedure changes, and per-sonnel training required for interim operation.
I attended and participated in the ASLB hearings concerning interim oper-ation as a PGE witness and have been responsible for the BN-21 1086 046 78200so({[2/;p
CFSP 417 and CI #2D Page 2 of 6 B.
D.
Withers operation of the Trojan Nuclear Plant since it returned to operation pending modification of the Control Building.
3.
The purpose of this affidavit is to add ess, in part, Coalition for Safe Power's Contention No. 17,. Ich reads as follows:
Performance of modification work will hamper the ability of plant operators to respond to any emergency properly and thus poses an undue risk to the public health and safety.
and Consolidated Intervenors' Contention No. 2d which reads as follows :
Licensee has not shown that there will be adequate fire protection at the Trojan plant during modifications in the following areas:
d)
Sufficient fire brigade access exists and will be maintained.
4.
The plan for the modification program has been devel-oped to be compatible with Plant operations under both normal and emergency conditions.
The affidavit of Mr.
E.
W.
Edwards on Coalition for Safe Power's Contention No. 17 identifies those areas where the modification work will be performed and also identifies potential interferences with access.
This affidavit will explain how PGE has identified all instances in which the modification work might interfere with the ability of Plant operators to respond to an emergency, in-cluding a fire, and will explain why the modification work will not cause such interferences.
BN-21 1086 047
s CFSP #17 and CI #2D Page 3 of 6 B.
D.
Withers 5.
In order to respond properly to an emergency, Plant operators must be able to react to visual and audible signals provided by Control Room instrumentation.
In some cases per-sonnel may have to operate equipment from remote locations outside the Control Room, thus, access to such locations must be assured.
Therefore, proper response to any emergency re-quires that Plant personnel be able to function properly within the Control Room and to reach remote locations in other parts of the Plant.
In addition, fire brigades must have access to a fire, wherever it might be located.
6.
PGE has reviewed Mr. Edwards' affidavit and has deter-minted that it correctly identifies all areas of the Plant where the modification work will be performed and all potential interferences with access by the modification work.
7.
In the event of a fire or other emergency within any of the areas where the modification work will be performed, Plant personnel would need access within such area.
Should such a fire or other emergency arise, modification work would be halted and construction workers would be instructed to leave the area and report to their supervisor outside the Plant buildings to await further instructions.
This will be part of the instruction given to workers on site for the modi-fication program, and the presence of these workers would not hamper the ability of Plant personnel to take effective action with respect to a fire or o':her emergency within such areas.
BN-21 1086 048
CPSP #17 & CI #2D Page 4 of 6 B.
D.
Withers 8.
PGE has also reviewed the modification work to ascer-tain whether there are any remote locations (as discussed in paragraph 5 above) within or adjacent to the work areas ident-ified in Mr. Edwa rds ' affidavit to which Plant personnel may need access during an emergency.
The only such remote loca-tions are:
East Emergency Diesel Generator Room at el. 45' in the Turbine Building West Engineered Safety Feature Switchgear Room at el.
69' in the Turbine Building Load Centers B12 and B06 (non-safety-related) at el.
69' in the Turbine Building East Electrical Auxilia_ ries Rocm and Batteries at el.
61'/65' in the Coatrol Building 9.
For each of the remote locations identified above, PGE has determined that at least one alternate access path is available which would be totally unobstructed by the modifica-tion work.
Accordingly, the modification work will not com-promise the ability of Plant personnel to reach such locations during an emergency.
10.
With respect to each of the specific instances identi-fied in paragraphs 6-8 of Mr. Edwards' affidavit where the modification work could involve potential interference with access paths, we have again determined that the modification work will not compromise the ability of Plant personnel to respond during an emergency, including a fire.
The limitation on access at el. 45' in the Turbine Building (Edwards' affida-vit, paragraph 6) is not in an area where safety-related BN-21 1086 049
CFSP #17 and CI #2D Page 5 of 6 B.
D.
Withers equipment is located and would not limit personnel access.
The stairway to the Visitors' Gallery above the Control Room and the ladder to the Turbine Building roof and crane cab (Edwards' affidavit, paragraph 7) do not provide access to re-mote locations containing safety-related equipment or to any equipment needed for normal operation.
In any event, there is another existing access to the Visitor's Gallery, and as described in the affidavit of Mr. Edwards' (paragraph 7) another access will be provided to the Turbine Building roof and crane cao.
Finally, the potential interferences caused by workers in aisles ( Ed wa rd s ' affidavit, paragraph 7) will be no greater than those one would expect during routine Plant maintenance.
Even so, as described above, should an emergency arise, includ-ing a fire, modification work will be halted and construction workers will be instructed to leave.
11.
Only a small portion of the modification work will take place at el. 93' in the Control Building adjacent to the Control Room.
If noise from work in this area interferes with operations, the Shift Supervisor will halt the work and work methods will be changed to reduce noise to acceptable levels.
Additionally, a few construction workers would be required to be on the Control Room side of the walls during the drilling and bolting operations.
These individuals would be working away from areas requiring immediate operator attention or action.
Furthermore, their presence and actions in this area would be controlled by the Shift Supervisor to preclude their inadvertently interfering with operations in the event of an emergency.
Thus, the modification work will not hamper BN-21 1086 050
CFSP #17 and CI #2D Page 6 of 6 B.
D.
Withers the ability of operators in the Control Room to respond to an emergency.
12.
The foregoing discussion demonstrates that any poten-tial impacts of the modification work on the ability of Plant personnel to respond to an emergency or fire have been identi-fied, and that all necessary precautiens will be ta).en to pre-clude any adverse impacts of the modification work on the ability of such personnel to respond properly.
I, Bart D. Withers, of lawful age, being first duly sworn, state that I have reviewed the foregoing affidavit, and that the statements contained therein are true and correct to the best of my knowledge and belief.
JAWL BART D.
WITHERS STATE OF OREGON
)
County of
'alb#o[ )
SCRIBED AND SWORN TO before me this j[E day of SUp/< c., <_,#
/
1979.
a.* d u k n
PUBLIC FOR ORSC,////f 0N NOTARY
/
My Commission Expires
/
/
BN-21 1086 051
.e PROFESSIONAL QUALIFICATIONS OF BART D. WITHERS PRESENT POSITION General Manager, Trojan Nuclear Plant.
EDUCATION Idaho State University - BS in Chemistry (1956);
Naval Reactor Prototype Traf r.ing, Idaho Falls, Idaho, A1W (1963), S5G (1972); Westinghouse PRR Simulator Training (1974).
PROFESSIONAL DATA Registered Professional Engineer, California; Member, American Nuclear Society.
SUMMARY
1956-1962 Chemist 1962-1967 Watch Officer and Shif t Supervisor 1967-1969 Operations Manager 1969-1971 Operations Evaluation Manager 1971-1972 Staff Management 1972-1973 Plant Manager 1974-1976 Assistant Plant Superintendent 1977-1979 Plant Superintendent / General Manager EXPERIENCE Mr. Withers has been employed by Portland General Electric Company since 1974. His first 3 years were spent as Assistant Superintendent for the Trojan Nuclear Plant and since January 1, 1977 he has been the Plant Superintendent /0eneral Manager for the Trojan Nuclear Plant.
Mr. Withers was employed by Westinghouse Electric Corporation for 16 years in various positions related to operation and management of r. clear reactors.
He entered Westinghouse's training program and quali-fied as an Engineering Officer of the Watch supervising control room operation of a Naval Reactor Prototype.
Mr. Withers served as a Shif t Supervisor and then Operations Manager for a naval reactor prototype.
He was transferred to the Bettis Atomic Power Labora-tory as Manager of Operations Evaluation.
Mr. Withers worked in Staff Management of Naval Core Manufacturing before being assigned as the Plant Manager for the S5G Naval Reactor Prototype.
Before joining Westinghouse, Mr. Withers worked 2 years for Phillips Petroleum as a chemist at a plant which processed spent reactor fuel.
108r6 052