Record of 790320 Telcon W/D Ford of Ucs Re Participation in Facility Pipe Stress IssueML20133N130 |
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Site: |
Beaver Valley, 05000000 |
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Issue date: |
04/10/1979 |
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From: |
Beckham D NRC |
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To: |
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Shared Package |
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ML20133M133 |
List: |
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References |
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FOIA-85-301 NUDOCS 8508130383 |
Download: ML20133N130 (2) |
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Category:ARCHIVE RECORDS
MONTHYEARL-94-014, Rev 1 to Safety Analysis of Radiological Consequences of SBLOCA at U2 with Delayed CNMT Spray Actuation & NUREG-1465 Core Damage Progression1998-01-30030 January 1998 Rev 1 to Safety Analysis of Radiological Consequences of SBLOCA at U2 with Delayed CNMT Spray Actuation & NUREG-1465 Core Damage Progression ML20195D0221998-01-26026 January 1998 Rev 1 to Assessment of Doses in Unit 2 CR Due to Locked Rotor Accident at Unit 2 Assuming 18% Failed Fuel ML20195C6421998-01-16016 January 1998 Change 1 to Rev 1 of Calculation 456, Combined BV1-BV2 Control Room Doses Due to Waste Gas Sys Line Rupture Accident at BV1 ML20217J8361997-10-0202 October 1997 Rev 1 to DE&S-SR/EM01, Ampacity Derating Factors of Fire- Protected Conduits L-96-010, Safety Analysis of Eab,Lpz & CR Doses from Main Steam Line Break Outside of CNMT at U2 W/Increased Primary-to-Secondary Leakage (SG Apc)1997-02-25025 February 1997 Safety Analysis of Eab,Lpz & CR Doses from Main Steam Line Break Outside of CNMT at U2 W/Increased Primary-to-Secondary Leakage (SG Apc) L-95-008, Rev 2 to SA of Common CR Eab,Lpz Doses from MSLB Outside of CNMT at Unit 1 W/Increased Primary-to-Secondary Leakage1997-02-24024 February 1997 Rev 2 to SA of Common CR Eab,Lpz Doses from MSLB Outside of CNMT at Unit 1 W/Increased Primary-to-Secondary Leakage ML20195F2321997-01-24024 January 1997 Rev 0 to Calculation 93C1783.2-03, IPEEE Seismic Fragility (SPRA) Review for Beaver Valley Unit 2 Structures ML20195F2111997-01-23023 January 1997 Rev 0 to Calculation 93C1783.2-02, IPEEE Fragility Evaluation for Beaver Valley Unit 2 Development of Beaver Valley Unit 2 HCLPFs for Flat Bottom Tanks ML20133F3281997-01-13013 January 1997 Press Release I-97-03, NRC Staff to Meet W/Officials of Dl to Discuss Apparent Violations at Bvnp L-96-011, RCS & SG Isotopic Concentrations,Pre-Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity1996-12-19019 December 1996 RCS & SG Isotopic Concentrations,Pre-Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity L-96-012, Rev 1 to Unit 1 RCS & SG Isotopic Concentrations,Pre- Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity1996-12-19019 December 1996 Rev 1 to Unit 1 RCS & SG Isotopic Concentrations,Pre- Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity L-96-021, Rev 0 to RG 1.145 Short-Term Accident X/Q Values for Eab & LPZ Units 1 & 2 Based on 1986-1995 Observations1996-12-19019 December 1996 Rev 0 to RG 1.145 Short-Term Accident X/Q Values for Eab & LPZ Units 1 & 2 Based on 1986-1995 Observations ML20134L2991996-11-20020 November 1996 Press Release I-96-75, Bvnp Rated 'Good' in Three Areas, 'Superior' in Fourth Area of NRC Assessment Rept ML20134D2211996-10-17017 October 1996 Press Release 96-145, NRC Asks Utility Licensees for Info on Concrete Containment Foundations at Nine Nuclear Plants ML20141F3021995-12-13013 December 1995 Battery Chargers & Inverters Anchorage Evaluation ML20141F2761995-11-30030 November 1995 Anchorage Evaluation for Various Instruments ML20096B4351995-11-0606 November 1995 SA of Common CR Doses from MSLB Outside of CNMT at U1 W/ Increased Primary-to-Secondary Leakage ML20141F2821995-10-30030 October 1995 GE Switchgear Anchorage Evaluation ML20141F3071995-05-0101 May 1995 Anchorage Evaluation for BAT-CHG-2 ML20195F2511994-01-31031 January 1994 Rev 0 to Calculation 93C1783-40, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1 DG Building ML20195F2441994-01-31031 January 1994 Rev 0 to Calculation 93C1783-07, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1 DG,EE-EG-1,2 ML20195F1961994-01-31031 January 1994 Rev 0 to Calculation 93C1783-13, Seismic Fragility (SPRA) Analysis,Beaver Valley Unit 1,Reactor Coolant Pump ML20128E3111992-11-17017 November 1992 Package Consisting of Insp Rept 50-344/PA-92-02 on 921021- 22.No Violations Noted.Major Areas Inspected:Shipping Documentation,Packaging/Package Insp,Labeling,Marking, Placarding,Vehicle Insp,Radiation & Contamination Surveys ML20079N0931989-12-31031 December 1989 Response to Questions Re Beaver Valley Unit 1 Impingement, Entrainment Monitoring rept,890131 Observation of Gizzard Shad Discharge of BVPS,1983 Annual Environment Rept Nonradiological ML20127C7441989-11-0808 November 1989 Partially Deleted Incident Rept 1-89-97 Dose Assessments & Associated Hpes Involvong Rj Brooks & Assoc Steam Generator Fosar Activities at Facility ML20247N1491989-09-26026 September 1989 Handout on Beaver Valley Unit 2 MSIV Mod & Test Program ML20247R3711989-09-18018 September 1989 Package of Three FOIA Requests ML20127A5651989-09-11011 September 1989 Package of Handwritten Radiological Work Sheets Re Steam Generator Annulus Secondary Side Hand Hole Insps L-89-021, Rev 0123 to ERS-SFL-89-021, Safety Analysis of Dose Consequences of Locked Rotor Accident at Beaver Valley Power Station 1 w/18% Fuel Failure,Exclusion Area Boundary,Low Population Zone,Control Room1989-07-28028 July 1989 Rev 0123 to ERS-SFL-89-021, Safety Analysis of Dose Consequences of Locked Rotor Accident at Beaver Valley Power Station 1 w/18% Fuel Failure,Exclusion Area Boundary,Low Population Zone,Control Room ML20155F8031988-09-0707 September 1988 Viewgraphs from Meeting on New Radwaste Facilities at Plants ML20195E0981988-05-10010 May 1988 Rev 1 to Calculation 456, Combined BV1-BV2 Control Room Habitability Due to Design Bases Accidents (Except LOCA) at BV1 ML20237D7901987-12-10010 December 1987 Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys ML20236Y5401987-11-26026 November 1987 RM-GW-101 Tech Spec Change Justification IA-87-725, Package Consisting of Requests for Addl Info Re Gpu Topical Repts TR-033, Methods for Generation of Core Kinetics Data for Retran-02 & TR-040, Steady-State & Quasi-Steady-State Methods Used in Analysis.... SPDS Meeting Summary Encl1987-11-20020 November 1987 Package Consisting of Requests for Addl Info Re Gpu Topical Repts TR-033, Methods for Generation of Core Kinetics Data for Retran-02 & TR-040, Steady-State & Quasi-Steady-State Methods Used in Analysis.... SPDS Meeting Summary Encl ML20236S4421987-11-20020 November 1987 Package Consisting of Requests for Addl Info Re Gpu Topical Repts TR-033, Methods for Generation of Core Kinetics Data for Retran-02 & TR-040, Steady-State & Quasi-Steady-State Methods Used in Analysis.... SPDS Meeting Summary Encl ML20149H9011987-10-0808 October 1987 Package Consisting of Repts of Licensee Telcons to Region V Re Incidents on 871007 & 1221 ML20245C6731987-10-0101 October 1987 Rev 1 to Calculation 211X-G(B)-290, Differential Settlement of SWS Lines Between Reactor & Safeguards. Oversize Info Encl ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20215G6621987-06-18018 June 1987 Package Consisting of Basic Nuclear Concepts - Lesson Objectives,Ja Dellavalle Undated Ltr & Northeast Utils, Thames Valley State Technical College Nuclear Engineering Technology Contract & Amend 1 ML20207F6471987-04-13013 April 1987 Doses in Combined Unit 1 & 2 CR Due to Waste Gas Sys Rupture at Unit 1 with 500 CFM Normal CR Ventilation ML20235P0461987-03-23023 March 1987 Package Consisting of Draft Board Notification 87-005 Re BNL Draft Rept on Spent Fuel Pool Accidents & Viewgraphs Concerning Generic Issue 82 on Beyond DBAs in Spent Fuel Pools ML20215H9621987-02-0505 February 1987 Package Consisting of NRR Presentation to ACRS Re 870115 Technical Meeting to Consider Generic Implications of Facility Feedwater Line Failure & J Rosenthal Failure of Main Feedwater Pipe 861209 Outline ML20151E8051987-02-0202 February 1987 Settlement of SWS Piping - Intake Structure to Valve Pit. W/Four Oversize Encls ML20211A0821986-10-0303 October 1986 Package Consisting of Summary Schedule Suppl & Variance Rept & Capital Project Request Summary ML20207S2341986-09-0909 September 1986 Affirmation Response Sheet Approving SECY-86-257, Request for Stay & Review of Appeal Board Decision in Shearon Harris Proceeding ML20207S2261986-09-0808 September 1986 Affirmation Response Sheet Partly Approving SECY-86-252, Commission Review of Shearon Harris Appeal Board on Environ Issues. Author Agrees W/Ofc of General Counsel Recommendation But Sees No Reason to Begin Rulemaking ML20207S2321986-09-0808 September 1986 Affirmation Response Sheet Disapproving SECY-86-254, Request for Hearing on Shearon Harris Exemption Request. Author Does Not Believe in Beginning Rulemaking to Change Requirement to 2-yr Rather than 1-yr Requirement IA-86-445, Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 8201311986-07-28028 July 1986 Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 ML20203H2851986-07-28028 July 1986 Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131 ML20204J1551986-07-0707 July 1986 Telcon of Significant Deficiency Rept SDR 86-09 Re Erratic Position Indication from Masoneilan Control Valves.Cause Unstated.Operators May Take Inappropriate Actions Based on Faulty Indication.Indicator Arms Upgraded 1998-01-30
[Table view] Category:TELEPHONE OR VERBAL CONVERSATION RECORD
MONTHYEARML20204J1551986-07-0707 July 1986 Telcon of Significant Deficiency Rept SDR 86-09 Re Erratic Position Indication from Masoneilan Control Valves.Cause Unstated.Operators May Take Inappropriate Actions Based on Faulty Indication.Indicator Arms Upgraded ML20207Q0811983-10-19019 October 1983 Record of Telcon W/G Kaerter on 831019 Re Alleged Cocaine Use at Wolf Creek Site.Related Documentation Encl ML20023D1811982-10-18018 October 1982 Telcon W/R Lanksbury on 821018 Re Analysis of Carbon Steel Not at Facilities.Nut Passed Hardness Test Used to Calculate Proof Test ML20133N1301979-04-10010 April 1979 Record of 790320 Telcon W/D Ford of Ucs Re Participation in Facility Pipe Stress Issue ML20098C8631975-10-0808 October 1975 Telcon W/Th Cox of NRC Re Financing for Units 4 & 5 1986-07-07
[Table view] |
Text
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AM 101913 6b MEMORANDUM FOR: File FROM: D. A. Beckman, Reactor Inspector
SUBJECT:
RECORD OF TELECON WITH MR. DAN FORD, UNION OF CONCERNED SCIENTISTS, MARCH 20,1979 Qg
@l:f I was called by Mr. Ford at 11:50 a.m. on March 20,1979 to discuss my CW participation in the Beaver Valley pipestress issue. Mr. Ford opened the
. conversation by stating that there seemed to be some confusion or lack of clear information regarding the ' chronology of activities leading to the identification of the problen and that he wanted to clarify what,-he could through me.
Y Mr. Ford repeatedly questioned me as to what part the erroneous check valve weights ptlayed in the discovery of the pipestress errors and when Region I became aware of the erroneous weights. I told him that the weights initiated the reevaluation which resulted in the anomalous PIPESTRESS/NUPIPE results and that I became aware of the check valve weight errors at or about the time of issue of the December 6 Licensee Event Report update (LER 78-53).
He further asked whether I knew what calculations had specifically been performed by the respective computer programs / hand calculations. I told him that I was aware of only those calculations discussed in the LER and in the Stone and Webster (S&W) report on the matter which I had reviewed (S&W Report to Duquesne Light Co. (DLC) which provided the S&W input to the LOl) .
Mr. Ford also asked if I was aware (or when I had become aware) that S&W
" abandoned" the use of PIPESTRESS in 1972 and that they made some (unspec-ified) modifications to the program. I responded that I was not aware of any'" abandonment" and that, to the best of my knowledge, the program was in use through at least 1974 when as-built 9erifications were performed on the design of the Beaver Valley 1 piping. I further stated that I was not aware of any pertinent modifications to the code during its tenn of use.
Mr. Ford then shifted his questioning to the chronology of the NRC internal handling of the problem, asking when I had prepared my input, to whom it was sent, when it was sent, etc. I told him that I had prepared the memo during the last week of December through early Ja'nuary and that the memo was fomarded through regional management to headquarters in mid-January.
He asked whether the time frames for handling seemed appropriate to me and whether I felt that the memo had been properly expedited. I responded that 8508130383 050703 PDR FOIA HERRMAN85-301 PDR
2 the memo had been given an appropriate priority based on the information available at any point in time and that as we learned more about the problem, the associated activities appeared to have been appropriately accelerated. We also discussed how track items are processed: Region -
IE:HQ - NRR. I received no specific questions about the subject track item except as noted above.
During the conversation I indicated that I had held informal discussions with NRR during and after preparation 4f the memo, including passing the informal copy to the NRR Licensing Project Manager. Mr. Ford asked for the names of the individuals to whom I had spoken. I gave him the aames of D. Wigginton and S. Hosford.
Mr. Ford asked if I knew when S&W, DLC, and/or NRC became aware of the error in the computer program; whether we were aware that it was erroneous during our inspections. I informed him that, while individuals within the NRC questioned the anomalous results, I knew of no one who was aware of the existance of an error or the specifics associated with the error prior to the meetings held by NRR from March 8,1979. He then asked whether I considered the S&W/DLC action on the evaluations conducted during October-December 1978 to be timely and responsive. I replied to the effect that I'was aware that S&W was expending a significant effort on resolution of the problem and that g telephone discussions with the site indicated that considerable DLC emphasis was being placed on S&W's activities but that I did not have first hand knowledge of the matter. I further stated that during g inspections I found that most of the pertinent engineering infor-ation was maintained at S&W, Boston, and, therefore, was unavailable to me, making it difficult for me to judge the timeliness and priorities given the matter. Issuance of the December 6 LER appeared timely and addressed the general concerns of this office at the time it was issued. During all other contacts with DLC and S&W, both organizations appeared to be free and open with the available information.
Mr. Ford then stated that he understood, apparently from hearing testimony of the Commission, that the December 6 issue of LER 78-53 constituted a closecut of DLC and S&W activity on the subject. I replied that his under-standing was incorrect. The last paragraph of that LER indicated that DLC Engineering was continuing a review of the matter., that further results of that review were to be provided by followup report, that I was aware of an ongoing effort in that area prior to the March 8 meetings, and that the licensee had issued a supplement to the LER subsequent to the issuance of the Show Cause Order on March 13.
e.s - o
o 3
Mr. Ford proceeded to ask about my professional background, education, professional experience, tenure with the NRC, etc. I responded that I had been with NRC since October 1977, hold an engineering degree, had been variously employed within the nuclear industry since 1969 including employment with civilian and Navy nuclear ship programs and an architect-engineer (other than S&W). I did not provide names or particulars of my previous employment.
Mr. Ford closed the conversation by asking my personal impressions of the handling that the pipestress matter had received from the NRC. I responded that I considered each phase of the NRC's review and subsequent action to be appropriate and technically responsive to the circumstances as the issue developed (similar to the response given in the fourth paragraph above). I stated that I was encouraged by the escalation of the matter once the
. seriousness of the errors was identified.
Mr. Ford then provided me with the phone number of the Union of Concerned Scientists' office in Washington, D. C. and asked that I call if I have any present or future concerns where they might be of assistance. The call was cordial and Mr. Ford offered no indication of his reactions to my statements. Messrs. R. Keimig and W. Raymond were present in my office
' for approximately the last twenty minutes of the thirty minute call but did not participate in the conversation and were not party to the telephone connection.
!f (L'
D. A. Beckman Reactor Inspector cc: E. Jordan, IE:HQ j '
W. Russell, NRR D. Wigginton, NRR E
.