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MONTHYEARML20137R7221985-11-22022 November 1985
Requests Presentation,Within 60 Days of Ltr Date,Of Plans for Assuring That Plant Designed Per FSAR Commitments & NRC Regulations.Plans Needed to Facilitate Decision Re Whether or Not Integrated Design Insp Will Be Conducted
Project stage: Other
ML20137J0181986-01-17017 January 1986
Submits Design Verification Activities Per 841122 Request. Actions Taken in Past & Activities in Process or Scheduled Identified for Providing Assurance That Facility Designed in Accordance W/Fsar Commitments
Project stage: Other
ML20153H1051986-02-18018 February 1986
Notification of 860228 Meeting W/Util in Bethesda,Md to Discuss Engineering Assurance Program & NRC Participation in Program
Project stage: Meeting
ML20154M5701986-03-10010 March 1986
Summary of 860228 Meeting W/Util Re Engineering Assurance Program & Independent Design Verification.Engineering Assurance Program Will Be Performed W/Nrc Participation to Assure Plant Built Per Util Commitments.W/O Encl Audits
Project stage: Meeting
ML20155K3431986-05-21021 May 1986
Forwards Evidence Documenting That Continuing S&W Detailed Design Reviews Provide Addl Assurance Sought by NRC That Design Process Used for Constructing Plant in Full Compliance W/Fsar & NRC Regulations
Project stage: Other
ML20199L7421986-07-0707 July 1986
Notifies of Review of Util Re Proposed Program for Completion of Engineering Assurance In-Depth Technical Audit. Proposed Engineering Assurance Program Acceptable for Integrated Design Insp or Idvp
Project stage: Approval
ML20214Q9331986-08-26026 August 1986
Forwards S&W Assurance Technical Audit Rept 52. Rept Provides Results of Phase I of Program for Completion of Engineering Assurance in-depth Technical Audits for Facility.W/O Encl
Project stage: Other
ML20211A2171986-10-0707 October 1986
Part 21 Rept Re Outside Containment Flooding Analysis Calculation.Initially Reported on 860407.Calculation Revised to Evaluate Lines Previously Exempted from Analysis & Flood Barriers Constructed Around Listed Areas
Project stage: Other
ML20207J8841986-12-19019 December 1986
Responds to 861114 Request to Address Issue of Whether Use of Stress Intensification Factor (SIF) of 1.0 for Branch Connections Technically Justified.Approach Similar to That Used at Shoreham Will Provide Technically Sound Resolution
Project stage: Approval
ML20207N2011987-01-0808 January 1987
Notification of 870123 Meeting W/Util in Bethesda,Md to Discuss Issues Re Stress Intensification Factor Used in Piping Stress Analysis
Project stage: Meeting
ML20155H9991987-02-23023 February 1987
Forwards S&W 870212 Engineering Assurance Corrective Action Status Rept Providing Status of Corrective Action Items Resulting from Engineering Assurance Audit 52
Project stage: Other
ML20214D7321987-05-15015 May 1987
Lists Efforts Towards Completion of S&W Confirmation Programs Prior to Fuel Loading,Per LS Rubenstein 870408 Commitment.Efforts Re Equipment Qualification Will Be Addressed in Separate Submittals
Project stage: Other
ML20214K3271987-05-20020 May 1987
Forwards S&W Engineering Assurance Corrective Action Status Rept,In-Depth Technical Audits. Rept Indicates That All of Action Items Resulting from Audit 52 Closed Based on Verification of Util Corrective & Preventive Actions
Project stage: Other
1986-05-21
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~9f 2NRC-7-135 Beaver Valley No. 2 Unit Project Organization Telecopy 9
Bo[$a"9 May 20, 1987 Shippingport. PA 15077 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
Beaver Valley Power Station Unit No. 2 Docket No. 50-412 Design Verification Activities - EA Audit No. 52
REFERENCES:
(a)
DLC Letter 2NRC-7-125, dated May 15, 1987, Mr. J. J. Carey to United States Nuclear Regulatory Commission (b) NRC Letter dated April 8,1987, Mr. Lester S. Rubenstein to Mr. J. J. Carey Gentlemen:
Enclosed is a copy of the Stone & Webster Engineering Corporation (SWEC)
Engineering Assurance (EA) Corrective Action Status Report, In-Depth Technical Audits, dated May 11, 1987.
This report indicates that all of the action items resulting from SWEC EA Audit No. 52 have been closed based on the Audit Team's verification of the Project's corrective and preventive actions.
Please refer to Reference (a) for the confirmation statements, regarding SWEC EA Audit No. 52, that the NRC requested that Duquesne Light Company provide prior to fuel loading.
This request was made by the NRC in Reference (b).
DUQUESNE LIGHT COMPANY
/
~ J J. Carey /
Senior (Tice President JD0/ijr NR/JD0/DSN/VRIF Enclosure AR/NAR cc: All with enclosure Mr. P. Tam, Project Manager Mr. J. Beall, NRC Sr.
Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr. E. V. Imbro, NRC Division of Reactor Inspection and Safeguards (5)
INP0 Records Center 8
0705280408 870520
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