ML18139B434
| ML18139B434 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 07/01/1981 |
| From: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM 403, NUDOCS 8107070331 | |
| Download: ML18139B434 (2) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND.., VIRGINIA 23261 July 1, 1981 R.}J.LEASBUBO Vici, ];';R.ESIDl'lNT NUCLl'lAR 0P1':RA:rlONS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear. Regulatory Connnission Washington, D. C.
20555 Gentlemen:
Serial No. 403 NO/DWS,Jr. :acm Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 RESPONSE TO NUREG 0737 POST-TM! REQUIREMENTS RELIEF & SAFETY VALVE TEST REQUIREMENTS ITEM II.D. l In accordance with the requirements of NUREG 0737 Post-TM! requirements, item II.D.l, Performance Testing of Power Relief Valve and Safety Valves, we are sponsoring a valve test program.
The scheduled commitment of NUREG 0737 to complete tests to qualify the reactor coolant relief and safety valves will not be complete by July 1, 1981.
Testing of the valves is being performed on a generic, industry wide basis by the Electric Power Research Institute (EPRI) and this valve test program is incomplete.
The valve test program is responsive to the requirements of NUREG 0737, item II.D.l.
The objective of the program is to perform full scale operability tests on a set of primary system relief and safety valves representative of those utilized in or planned for use in PWR' s, under conditions expected as a result of FSAR, cold overpressurization, and extended high pressure injection events.
Relief and safety valves installed on the North Anna 1 & 2 and Surry 1 &
2 Units are represented by valves being tested in the program.
North Anna 1 &
2 has a Masonellan relief valve model no. 20,000.
Surry 1 & 2 has a Copes-Vulcan relief valve model no. D-100-160.
North Anna 1 & 2 has a Dresser safety valve model no. 31759A.
Surry 1 & 2 has a Crosby valve & Gage safety valve model no. HB-BD-86.
Although testing is not complete, EPRI has been instructed to submit an Interim Data Report via EPRI Research Advisory Connnittee, Consumers Power Company, Mr. R. C. Youngdahl, Chairman.
This preliminary report includes all tests performed on or before June 19, 1981 and will be submitted generically by Consumers Power Company on or before July 1, 1981.
This submittal will explain the reasons for the program delays along with the revised completion date of valve testing.
l e
VIRGINIA ELECTRIC AND POWER COMPANY TO Harold R. Denton and Darrell G. Eisenhut We regret the delay of the test program.
We are encouraging EPRI to proceed toward completion as rapidly as possible.
cc:
Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Licensing Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Very truly yours,
- WJ{(~
R/ H. Leasburg Vice President - Nuclear Operations