Letter Sequence Supplement |
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MONTHYEARB11453, Forwards Addl Info Re SER Confirmatory Item 70 Concerning 260 Series Questions on QA Program During Operational Phase, Per Discussion During 850129 Telcon.Item Resolved1985-03-0101 March 1985
Forwards Addl Info Re SER Confirmatory Item 70 Concerning 260 Series Questions on QA Program During Operational Phase, Per Discussion During 850129 Telcon.Item Resolved
Project stage: Request
ML20133D9321985-07-24024 July 1985
Safety Evaluation Supporting Amend 12 to CPPR-113
Project stage: Approval
ML20133D9361985-07-24024 July 1985
Notice of Issuance of Amend 12 to CPPR-113
Project stage: Approval
ML18143B4431985-08-30030 August 1985
Submits Addl Info to Complete 850208 & 0520 Responses to Generic Ltr 83-28,Item 2.2 Re Description of industry-wide Approach to Vendor Interface Program Per Mar 1984 Nutac Recommendations
Project stage: Request
ML20138G7341985-09-26026 September 1985
Environ Assessment & Finding of No Significant Impact Supporting Exemption from Portion of GDC 4 Requirements of 10CFR50,App a Re Need to Analyze Large Primary Loop Ruptures as Structural Design Basis
Project stage: Approval
ML18144A0111985-11-0505 November 1985
Requests Partial Exemption from GDC 4,eliminating Protection Against Dynamic Effects of Postulated Pipe Rupture on Primary Sys Components & Piping,Per Generic Ltr 84-04. Snubbers Will Be Removed During 1986 Refueling Outage
Project stage: Other
ML18144A0441985-11-30030 November 1985
VEPCO Surry Units 1 & 2 Safety Balance Assessment for Elimination of RCS Main Loop Pipe Break Protective Activities
Project stage: Other
ML18144A0421985-11-30030 November 1985
VEPCO Surry Units 1 & 2 RCS Loads & Component Support Margins Evaluation of Elimination of RCS Main Loop Pipe Break Protective Devices
Project stage: Other
ML18144A0431985-11-30030 November 1985
VEPCO Surry Units 1 & 2 RCS Leakage Detection Assessment for Elimination of RCS Main Loop Pipe Break Protective Devices
Project stage: Other
ML18144A0401985-12-0303 December 1985
Forwards Repts in Support of 851105 Request for Exemption from GDC 4,eliminating Protection Against Dynamic Effects of Postulated Pipe Rupture on Primary Sys Components & Piping
Project stage: Request
ML18144A1531985-12-27027 December 1985
Notifies That Supplemental Info Re Partial Exemption Request for GDC 4 Discussed During 851219 Meeting Will Be Submitted by 860115.List of NRC Questions Encl
Project stage: Supplement
ML18149A0191986-01-14014 January 1986
Forwards Addl Info Re Request for Partial Exemption from GDC 4,per 851219 Meeting
Project stage: Meeting
ML18149A1441986-04-30030 April 1986
Application for Amends to Licenses DPR-32 & DPR-37,revising Tech Specs to Add License Condition Authorizing Rev to Reactor Coolant Pump & Steam Generator Support Design to Mitigate Pipe Rupture Events
Project stage: Request
ML18149A1461986-04-30030 April 1986
Proposed Tech Specs,Authorizing Rev to Reactor Coolant Pump & Steam Generator Support Design.Safety Evaluation Encl
Project stage: Other
ML18149A1431986-04-30030 April 1986
Forwards Discussion of Current Practices Re Use of 35% Enriched Oxygen w/open-circuit self-contained Breathing Apparatus to Meet Requirements of 10CFR20.103 in Response to 860327 Request.Fee Paid
Project stage: Request
ML18149A1641986-05-19019 May 1986
Summary of 851219 Meeting W/Util,Paul Munroe Energy Plants, Westinghouse & S&W in Bethesda,Md to Discuss Util 851105 & 1203 Submittals Re Exemptions from GDC 4.Presentation Handout Encl
Project stage: Meeting
ML20206J1021986-06-16016 June 1986
Safety Evaluation Supporting Amends 108 to Licenses DPR-32 & DPR-37
Project stage: Approval
ML20206J0961986-06-16016 June 1986
Amends 108 to Licenses DPR-32 & DPR-37,permitting Plant Operation W/Reactor Coolant Pump & Steam Generator Supports Redesigned Per 860512 Amend to GDC-4,10CFR50,App a (51FR12502)
Project stage: Other
1985-07-24
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261
- w. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS December 27, 1985 Jir. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Lester S. Rubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. 1 AND 2 PARTIAL EXEMPTION FROM GENERAL DESIGN CRITERION 4 REQUEST FOR ADDITIONAL INFORMATION Serial No.
NO/JDH/acm Docket Nos.
License Nos.
85-136B 50-280 50-281 DPR-32 DPR-37 We met with members of your staff on December 19, 1985 in your office in Bethesda, M~ryland to discuss our partial exemption request from General Design Criterion 4 for Surry Power Station freference: our November 5, 1985 (Serial No.85-136), and December 3, 1985 (Serial No. 85-136A) letter![]. At that meeting, your staff identified a need for supplemental information in five areas.
The specific items are listed in the Attachment.
Because we are working expeditiously to provide you with the requested information, please notify us immediately if our understanding of the concerns is incorrect.
We currently anticipate submitting the supplemental information by January 15, 1986.
As we stated at that meeting the increase*s in plant reliability and maintainability, reductions in cost and personnel exposure are substantial. We appreciate your efforts to support our schedule for implementing the requested relief_
during the upcoming 1986 Surry refueling outages.
Very truly yours, Attachment 8512310361 851227 PDR
'ADOCK 05000280 P
PDR r-*------*
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-~ADgp
.PWR - A/BC's TECH SUPPORT' AD - J. KNIGHT (ltr only)
EB (BALLARD)
EICSB (ROSA)
PSB (GAMMILL)
RSB (BERLINGER)
FOB (BENAROYA)
e VIRGINIA. ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton cc:
Dr. J. Nelson Grace Regional Administrator NRC Region II Mr. Donald J. Burke NRC Resident Inspector Surry Power Station Mr. Terence L. Chan NRC Surry Project Manager PWR Project Directorate #2 Division of PWR Licensing-A
.it e
NRC QUESTIONS RE GDC-4 EXEMPTION REQUEST SURRY POWER STATION ATTACHMENT
- 1.
Provide a summary of piping stresses (similar to Table 1 of the Loading Evaluation in our December 3, 1985 letter) including the main steam and pressurizer surge line breaks (i.e. the controlling breaks).
- 2.
Provide a comparison of the maximum pipe stress locations between the existing and.proposed configurations for seismic condition and the controlling break.
- 3.
Provide a comparison of the component support Factors of Safety (similar to Table 2 of the Loading Evaluation in our December 3, 1985 letter) for the existing and proposed configurations including the controlling loads of main steam and pressurizer surge line breaks.
- 4.
Present the Reactor Coolant Pump (RCP) frequencies and modes for significant RCP motion.
- 5.
Discuss verification of the input geometry used in the computer models.
-~
