ML18153C558
| ML18153C558 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/04/1991 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 91-082, 91-82, NUDOCS 9103080262 | |
| Download: ML18153C558 (3) | |
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VlRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 4, 1991 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 OUTAGE MODIFICATION ACTIVITIES Serial No.
NO/RBP Docket No.
License No.91-082 R1 50-281 DPR-37 On February 6, 1991, a meeting was held with the NRC to discuss the schedule and planned activities for the upcoming Surry Unit 2 outage. The outage is scheduled to begin on March 29, 1991 and is planned to be 67 days in duration. As discussed in the meeting, a number of activities for this outage are being rescheduled within our five year plan. This letter identifies those activities and provides the reasons for their rescheduling.
RESCHEDULED ACTIVITIE$
Pressurizer Safety Valve Discharge Piping Supports This modification provides safety valve discharge piping supports to accommodate water (loop seal) discharge from the safety valves. While this issue is different and separate from the safety valve setpoint issue, the setpoint resolution may significantly impact piping support design requirements. Therefore, implementation of piping support modifications will follow resolution of the setpoint issue. We are presently evaluating the use of a steam trim package on the safety valves with the loop seals drained. Elimination of the loop seal design will significantly reduce the discharge piping support requirements, which will likewise reduce the amount of pipe support work and associated radiation dose expenditure for the modification.
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Control Ro*om Design Review The following modifications had been previously identified to address human engineering deficiencies (HEDs) evaluated during the Control Room Design Review (CADA):
Controller and Switch Modifications Indicator, Recorder, and Controller Modifications EOG and Auxiliary Shutdown Panel Replacements Flow Indication and Recorder Modifications
- Pressurizer Spray Valve Position Indication Status Light Modifiqations These items are being rescheduled primarily to avoid excessive control room activity during the Surry Unit 2 outage, since Unit 1 will be operating and the Units 1 and 2 control rooms are shared. There will already be a significant amount of activity in the control room related to the air handling unit modifications being performed during this outage.
As indicated during the February 6, 1991 meeting, it is our intention to reassess a number of these CRDR items in view of operational experience and observed operator performance on the simulator. We intend to close out remaining CADA items either by completion or by some other disposition based on reassessment by the end of 1994.
This schedule is consistent with our commitment for completion of long term CADA modlfications.
RCP Thermal Barrier Component Cooling Modification Tha proposed modification involves the addition of qualified component cooling water system valves to automatically isolate the system at the containment penetration in the event of a RCP thermal barrier rupture. The materials (i.e., isolation valves) required for this modification cannot be procured in time to support this outage. However, the required penetration work will be performed during the outage in anticipation of future installation of the isolation valves at the next refueling outage.
Component Cooling "C" Heat Exchanger Replacement The "C" heat exchanger continues to be acceptable for continued operation.
Replacement of this heat exchanger is not necessary during this outage, but is being considered for non outage replacement. A radiation monitor will be installed on the existing component cooling heat exchanger during this outage consistent with the separate commitment for upgrading these monitors. This will complete the radiation monitor upgrade for the four component cooling heat exchangers.
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Installation of New Cavity Seal Ring This item required evaluation of a new design for the cavity seal ring. Although this evaluation was completed, the new design could not be installed for use during the Unit 1 refueling outage, due to dimensional variations in the as-built condition of the sealing surfaces which exceeded the design tolerances for the new cavity seal. The existing cavity seal ring design was tested and installed for the Unit 1 refueling outage.
The existing cavity seal ring for Unit 2 will also be tested and used during the Unit 2 refueling outage. The test provisions for confirming leak-tightness of the passive seal on the existing cavity seal rings will be formally proceduralized prior to testing the Unit 2 seal ring.
As discussed in our February 6, 1991 meeting, it is our intention to complete the remaining items during the Unit 2 outage. If any additional commitment items have to be rescheduled due to materials unavailability or other reasons, we will advise you of tho'se items as we become aware of them.
If you have any questions regarding this submittal, please contact us.
Very truly yours,
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W. L. Stewart Senior Vice President - Nuclear cc:
Mr. S. D. Ebneter Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station