ML19326E195
| ML19326E195 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/25/1980 |
| From: | Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8007280444 | |
| Download: ML19326E195 (2) | |
Text
VIRGINIA ELucrnIc Axn Pownn Co>uuNY nxenxoxn,vxmoxx1A canst July 25, 1980 Mr. Harold R. Denton, Director Serial No. 629 Office of Nuclear Reactor Regulation N0/FHT:smv Attention:
Mr. B. Joe Ioungblood, Chief Docket No. 50-339 Licensing Branch No. 1 License No. NPF-7 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
EPRI SAFETY AND RELIEF VALVE TEST PROGRAM APPLICABILITY NORTH ANNA POWER STATION UNIT 2 In support of your staff's efforts to complete the Full Power Safety Evaluation Report (SER) for North Anna Unit 2, we are supplying the following supplemental information.
1.
Virginia Electric and Power Company is participating in the EPRI/NSAC Safety and Relief Valve Test Program as described in their " Program Plan for the Performance Verification of PWR Safety / Relief Valves and Systems", dated December 13, 1979.
2.
We are monitoring the Program to insure that:
a)
The results will be applicable to Surry and North Anua, and b)
It will provide sufficient information to allow qualification of our specific safety and relief valves and associated piping and supports under expected operating conditions for design basis transients and accidents.
3.
We will forward, by July 1, 1981, the following information:
a.
Evidence, supported by test, of safety and relief valve capa-bility to operate and function properly for expected operating and accident (non-ATWS) conditions.
The testing should demon-strate that the valves will open and reclose under the expected flow conditions.
b)
Evidence or correlation to substantiate that the valves tested in the program demonstrate the capability of the "as-installed" primary safety and relief valves to operate and function properly
-We will show that the test conditions used are equivalent to, or more limiting than, the expected operating and accident " conditions as prescribed in the FSAR.
We will 8 0 0 7 280 L/ 4 y
VinoNIA EttcTalC AND Powrn COMPANY TO Mr. Harold R. Denton, Director also account for the effect of "as-built" safety and relief valve discharge piping on valve operability if the configuration is different from the "as-installed" piping.
c)
Test data including criter' a for success and failure of valves i
tested will be provided for review and evaluation.
This test data will permit plant specific evaluation of discharge piping and supports which are not tested directly.
4.
We will submit evidence supported by test to qualify our specific plant block valves under expected operating conditions for design basis transients and accidents by January 1, 1982.
Very truly yours, Manager - Nuclear Operations and Ma'.ntenance FHT/smv:SY2 cc:
Mr. James P. O'Reilly g
Office of Inspection and Enforcement Region II Atlanta, Georgia 30303 9
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