Letter Sequence Other |
|---|
|
|
MONTHYEARML20087G1681982-03-31031 March 1982
Rev 1 to EPRI PWR Safety & Relief Valve Test Program Guide for Application of Valve Test Program Results to Plant-Specific Evaluations
Project stage: Other
ML18150A1361984-10-31031 October 1984
Forwards Response to NRC 840209 Request for Addl Info Re NUREG-0737,TMI Action Item II.D.1 Concerning Relief & Safety Valve Testing.Info Prepared by S&W,Per
Project stage: Request
ML20132D4661985-09-20020 September 1985
Advises That Addl Info Re Performance Testing of Relief & Safety Valves,Per NUREG-0737,Item II.D.1,will Be Forwarded by 851031 Due to Input Required by S&W & Westinghouse
Project stage: Other
ML18144A0061985-10-31031 October 1985
Forwards Addl Info Re NUREG-0737,Item II.D.1 on Performance Testing of Relief & Safety Valves,Per 850920 Commitment. Response to Request Numbers 2,4,5,6b & 7 Also Encl.Remaining Info Will Be Submitted by 860228
Project stage: Other
ML18149A0511986-02-28028 February 1986
Forwards Addl Info Re NUREG-0737,Item II.D.1, Performance Testing of Relief & Safety Valves, Per 850813 Request. Feedline Break Accident Analyzed Using Retran Sys Transient Analysis Computer Code.Two Loop Model Utilized
Project stage: Other
PNO-II-87-061, on 870920,automatic Trip from 100% Power Occurred.Caused by Phase to Ground Fault in B Phase at Electrical Connection on B Reactor Coolant Pump.Safety Injection Signal Reset1987-09-21021 September 1987
PNO-II-87-061:on 870920,automatic Trip from 100% Power Occurred.Caused by Phase to Ground Fault in B Phase at Electrical Connection on B Reactor Coolant Pump.Safety Injection Signal Reset
Project stage: Request
ML18152A5961987-11-13013 November 1987
Responds to 870921 Request Re Completion of Review of NUREG-0737,Item II.D.1 - Safety & Relief Valve Testing for Units 1 & 2. Method Developed & Procedures Will Be Revised to Verify Operability of Pressurizer Safety Valves
Project stage: Other
1985-09-20
[Table View] |
Advises That Addl Info Re Performance Testing of Relief & Safety Valves,Per NUREG-0737,Item II.D.1,will Be Forwarded by 851031 Due to Input Required by S&W & Westinghouse| ML20132D466 |
| Person / Time |
|---|
| Site: |
Surry  |
|---|
| Issue date: |
09/20/1985 |
|---|
| From: |
Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
|---|
| To: |
Harold Denton, Varga S
Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM 85-615, TAC-44622, TAC-44623, TAC-44633, NUDOCS 8509300181 |
| Download: ML20132D466 (2) |
|
Similar Documents at Surry |
|---|
|
Text
_ _ _
k VIHO1NIA l$LECTHIC AND l'OWI!M COMI%NY Ricnwoxn.VIHGINIA 2H261 W.L. STEWART Vaca Psamapuut Na ca. eau OPERATIONS September 20, 1985 Mr. Harold R. Denton, Director Serial No.85-615 Office of Nuclear Reactor Regulation N0/WRB:cfm Attn:
Mr. Steven A. Varga, Chief Docket Nos.
50-280 Operating Reactor Branch No. 1 50-281 Division of Licensing License Nos.
DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D. C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. 1 AND 2 ADDITIONAL INFORMATION RELATED TO NUREG-0737, ITEM II.D.I PERFORMANCE TESTING OF RELIEF AND SAFETY VALVES In your letter dated August 13, 1985 you requested additional information related to the above subject. The information requested requires input from our architect-engineer (Stone & Webster) and vendor (Westinghouse),
4 d
as well as Vepco. The information is to be forwarded to us by October 7, 1985. It will then be reviewed and forwarded to you by October 31, 1985.
Very truly yours, i
I a
i W. L. Stewart ge4 0
93 0 8
290 P
D VinotwtA Etrcrste awn Powra Courawy to cc:
Dr. J. Nelson Grace Regional Administrator NRC Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. Steven A. Varga, Chief Operating Reactor Branch No. 1 Division of Licensing