ML18153C209
| ML18153C209 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/01/1990 |
| From: | Buckley B Office of Nuclear Reactor Regulation |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 9005040229 | |
| Download: ML18153C209 (3) | |
Text
- Do~ket No. 50-280 Mr. W. L. Stewart Senior Vice President - Nuclear Virginia Electric and Power Company 5000 Dbminion Blvd.
May 1, 1990 DISTRIBUTION.
Docket File NRC & LPDRs PD22 Rdg File SVarga 14/E/4 GLainas 14/H/3 DMi 11 er BBuckley OGC e
Glen Allen, Virginia 23060 EJordan MNBB-3302 ACRS(lO)
Dear Mr. Stewart:
MSi nkul e RI!
SUBJECT:
SURRY UNIT 1 - PARTICIPATION IN NRC-FUNDED RESEARCH PROGRAM The purpose of this letter is to request Virginia Electric and Power Company 1s (VEPC0 1s) participation in an NRC-funded research program relating to radiation effects on reactor pressure vessel (RPVs) supports. This program, taken to completion, will address qualitatively the consequences of RPV support strutture failure for designs different from those at the Trojan facility where most of our efforts have been focused to date.
I have already discussed this program briefly with D. Sommers of your staff.
I would very much appreciate if you would provide one copy each of the requested information delineated in the enclosure.
The requested information should be forwarded to:
Dr. John O'Brien Division of Engineering Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555
Enclosure:
As stated cc w/enclosure:
See next page Sincerely, Ortginal signed by Bart C. Buckley, Seni~r Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 0Fc ___ =~LA:PDII-2 _______ :PM:P~~...,_ ___ :D:~PDII=2 ______ = ______________ = ______________ =_ -----------
NAME __ :_ -~~r _________ :aauc~~f1kd __ ;HB_r_'w _______ ; ______________ : _______
- ______ ~-------------
DATE
- 04/~ 90
- 04/5-0/90
- Q_~ \\!90 OFFICIAL RECORD COPY Document Name
RPVS SURRY
/
9005040229 900501 PDR ADOCK 05000280 P
\\
f l
e Mr. W. L. Stewart Virginia Electric and Power Company cc:
Michael W. Maupin, Esq.
Hunton and Williams Post Office Box 1535 Richmond, Virginia 23212 Mr. Michael R. Kansler, Manager Surry Power Station Post Office Box 315 Surry, Virginia 23883 Senior Resident Inspector Surry Power Station U.S. Nuclear Regulatory Commission Post Office Box 166, Route 1 Surry, Virginia 23883 Mr. Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Mr. W. T. Lough Virginia Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23209 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 C. M. G. Buttery, M.D., M.P.H.
Department of Health 109 Governor Street Richmond, Virginia 23219 e
Surry Power Station Attorney General Supreme Court Building 101 North 8th Street Richmond, Virginia 23219 Mr. E. Wayne Harrell Vice President - Nuclear Operations Virginia Electric and Power Company 5000 Old Dominion Blvd.
Glen Allen, Virginia 23060 Mr. J. P. 0 1Hanlon Vice President - Nuclear Services Virginia Electric and Power Company 5000 Old Dominion Blvd.
Glen Allen, Virginia 23060 Mr. R. F. Saunders Manager - Nuclear Licensing Virginia Electric and Power Company 5000 Old Dominion Blvd.
Glen Allen, Virginia 23060
J
~
REQUESTED INFORMATION FOR THE NRC-FUNDED RESEARCH PROGRAM RELATING TO THE EFFECTS ON REACTOR PRESSURE VESSEL SUPPORTS Enclosure Please provide the following information needed for the consequence evaluation of embrittled RPV support failure of Surry Unit 1:
- 1.
DRAWINGS Stone & Webster (S&W) Drawings 11448-FV-7 Series, Reactor Neutron Shield Tank.
S&W Drawings 11448-FP-8A Series, Reactor Coolant Piping.
- 2.
REPORTS AND COMPUTER ANALYSIS MODELS, S&W Cale. No. 14937.12-NM(B)-286-BA, 11 Primary Component Support Snubber Elimination Study Normal Operating and Seismic Loads, 11 10/~/85, and the computer model.
S&W Cale. No. 14987.12-NM(B)-292-BA, 11 Dynamic Analysis of Limiting Ruptures for Leak-Before-Break, 11 11/27/85, and the computer model.
S&W Cale. No. 14937.12-NP(B)-002-X, 11 Reactor Coolant Loop Branch Connection Displacements and Pressurizer Surge Line Evaluation Upon Removal of Equipment Snubbers - Surry I, 11 10/10/85.
S&W Cale. No. 12241-NM(B)-213-BD, 11Multiple Loop Seismic Analysis, 11 12/6/85, and the computer model.
S&W Cale. No. 11448-GB-14, Part C, 11Stress Analysis of the Reactor Vessel Support Sliding Foot Assembly.
11 S&W Cale. No. 11715-NM(B)-BF-161, 11 Revised RPV Nozzle Support Stiffness, 11 4/5/76.
S&W Cale. No. 12241-NM(B)-237-BB, Rev.l, 11 RPV Support System Stiffness and Westinghouse Interface Model,
11 3/11/87.
S&W Cale. No. 15253.28-NM(B)-317-BB, 11 Dynamic Analysis of the Neutron Shield Tank.
11 Project Topical Report for Unit No*. 1 Surry Power Station - Life Extension Evaluation of the Rector Vessel Support, Stone & Webster Engineering Corporation, 10/10/86.
- 3.
SUPPORT STIFFNESSES FOR STEAM GENERATOR ANO REACTOR COOLANT PUMPS - This information is needed if it is not included in the reports or computer models requested.