ML20247D996
| ML20247D996 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/04/1989 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 89-330, GL-88-17, NUDOCS 8905260091 | |
| Download: ML20247D996 (2) | |
Text
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A VIRGINIA ELECTRIC AND POWER COMPANY RICllMOND, VIRGINIA 23261
[
May 4, 1989 United States Nuclear Regulatory Commission Serial No.89-330 Attention:
Document Control Desk NAPS /PAK:
bgp R1 Washington, D.C.
20555 Docket No.
50-339 License No. NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 RACTOR COOLANT STANDPIPE INSTALLATION Generic. Letter 88-17 Loss of Decay Heat Removal, requi red programmed enhancements consisting of hardware installations and/or modification' implementation.by the end of the first refueling outage that is initiated 11 months or later following receipt of the letter, or by the end of the secord refueling outage following receipt of the letter, whichever occurred first.
- The Virginia Electric and Power Company response to NRC Inspection Report 88-01 dated April 29, 1988, and responses to Generic Letter 88-17 dated January 6, 1989 and February 3, 1989 conmitted to the installation of a permanent reactor vessel standpipe arrangement during the 1989 refueling outage.
Design Change Package (DCP) 88-12 was developed and implemented to direct the installation activities for the new standpipe as previously conmitted.
However, the modification will not be completed during the 1989 refueling outage because necessary engineering could not be performed due to inaccessibility of the containment during the previous operating cycle.
Extensive engineering was required to design customized piping supports to avoid interferences with existing equipment in congested areas.
This subsequently increased the projected installation time.
Mechanical and electrical work for DCP-88-12 has been completed during the 1989 refueling outage except for the following:
a)
Installation of the local indicator scale on the standpipe.
b)
Installation of additional supports for the capillary tubing connected to the Rosemount transmitter.
c)
Installation of the Mndpipe drain line to the existing transmitter j
blowdown header.
d)
Installation of the spool pieces to connect the system to the Reacter Coolant.
8905260091 890504
[h PDR ADDCK 05000339.
O P
PNV l6 J
lJ e)
Replacement of damaged magnetic flag indicator.
f)'
I'ns'tallation of one transmitter seal support.
g)
Final painting.
h)
Final calibration and testing.
To ensure the safety of other containment systems remains unaffected the standpipe modification was left in the following condition:
1)
Components were seismically secured and verified by a stress analysis based on the as-built configuration.
2)
The new system is disconnected from any existing RCS piping.
3)
Wiring is complete and deenergized until completion of the modification.
4)
The RCS boundary will be restored with flanges per the existing unmodified design.
Appropriate measures have been taken to ensure the new level indication system will be operable prior to the next entry into a reduced inventory condition (i.e., vessel level less than three feet below the reactor vessel flange) and therefore, will not adversely impact overall plant safety.
If you have any questions or require additional information, please contact us.
Very truly yours, i
/ r W. L. Stewart U
Senior Vice President - Power l
Attachment cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
Suite E900 Atlanta, GA 30323 Mr. J. L. Caldwell 4
NRC Senior Resident Inspector North Anna Power Station i
1
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