ML20076H085
| ML20076H085 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/07/1983 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 326, NUDOCS 8306160405 | |
| Download: ML20076H085 (2) | |
Text
_____________________
T.
VIROINIA ELECTRIC AND POwnu COMPANY Rtcunown,VinoINIA 20261 W.L.SinwART Vses Passmewr weet=== ors = mon.
June 7, 1983 Mr. Harold R. Denton, Director Serial No. 326 Office of Nuclear Reactor Regulation PSE&C/BSD/ses:0498C Attn: Mr. Robert A. Clark, Chief Docket Nos.
50-338 Operating Reactors Branch No. 3 50-339 Division of Licensing U. S. Nuclear Regulatory Commission License Nos.
NPF-4 Washington, D. C.
20555 NPF-7 Gentlemen:
GENERAL DESIGN CRITERIA 17 ANALYSIS NORTH ANNA UNIT NOS. 1 AND 2 The purpose of this letter is to respond to your letter of January 11, 1983, Serial No. 040, and attached Safety Evaluation.
The two items addressed in the Safety Evaluation are the possible overvoltage on motor control center contactor coils and the resolution of motor operated valve rerating or replacement.
The starter manufacturer was unable to document the acceptability of overvoltage on contactor coils, therefore, Vepco will perform tests of the coils to determine the effects of the overvoltage and determine the resolution required by the results of the tests.
The test results and any resolution and related schedule will be submitted when it is available. We presently anticipate this submittal will be available by January 31, 1984. As discussed in our October 26, 1982 letter, Serial No. 608, we believe the overvoltage is not a serious concern.
We have continued our effort to resolve which motor operated valves can be
.rerated and which may require modification or replacement of the motor operator.
Based on information from the motor operator manufacturer 80 of the units can be rerated, one must have the operator replaced and 47 need further information prior to determining if they need to be rerated or replaced.
He are continuing our contact with the valve manufacturers in an effort to confirm the torque requirements specified for the M0V's by the motor operator vendor.
Response from the valve manufacturers has been much slower than originally expected. He anticipate their response will continue to be slow and that some vendors may never respond as they no longer manufacture nuclear valves. He are initiating engineering of the modification based on the information received from the motor operator vendor.
In view of these facts, we estimate the completion of our MOV studies will occur by May 1, 1984.
The results of our studies will be provided to you upon completion.
8306160405 830607 PDR ADDCK 05000338
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VamOINIA Exzerenc AM,D rOWEB COMPANY TO He have previously indicated, in our June 4, 1982 letter, Serial No. 316, to you, our modifications (including torque switch limiter plate installation and M0V replacement when required) are scheduled for completion by the end of the second refueling outage of each unit after September 1, 1982.
By October 15, 1983, we will provide you an update on our progress and our plan regarding MOVs for which the MOV manufacturer or valve manufacture has been unable to provide complete information. Untti this information is complete, procurement schedules for possible replacement / upgrade cannot be finalized.
We will attempt to provide a permanent schedule in a December 15, 1983 update.
Very truly you s, l
V
. L. Stewar cc: Mr. R. C. DeYoung, Director NRC O'fice of Inspection and Enforcement Div!;ian of Reactor Operations Inspection Washi.v; ton, D. C.
20555 Mr. J. P. O'Reilly Regional Administrator - Region II Mr. M. B. Shymlock Resident Inspector - North Anna
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