ML20136F636
| ML20136F636 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/14/1985 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Butcher E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 85-723A, NUDOCS 8511220162 | |
| Download: ML20136F636 (3) | |
Text
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VInOINIA ELactmIC AND POWER COMPANY RIcnnown,VINGINIA 202G1 4
W.L.SeawAmr
-Vaca Pasannant.
- Noca. man oramassons -
November 14, 1985 c
Mr. Harold R. Denton, Director Serial No.: 85-723A Office of Nuclear Reactor Regulation N0/DAS:vlh
-Atta:
Mr. Edward J. Butcher, Acting Chief Docket No.: 50-338 Operating Reactors Branch No. 3 License No.:NPF-4
.U. S.
Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY
' NORTH ANNA POWER STATION UNIT 1 REVISED REQUEST F)R SCHEDULAR EXEMPTION REGARDING CERTAIN APPENDIX "R" MODIFICATIONS In our letter, Serial 85-431A dated September 14, 1984, we requested a schedular' exemption pursuant to 10 CFR 50.12(a) regarding certain Appendix R modifications.
In that letter, we requested that our implementation schedule for the subject modifications, based on the provisions of 10 CFR 50.48(c) (4),. be extended from the 1984 refueling outage to.the next refueling outage.
Our latest letter, Serial.85-723
-dated October 21, 1985, modified the schedular exemption request regarding these modifications, based on the rescheduling of Unit i refueling outage and associated subsequent difficulties in completing the modifications during the outage.
Based on a " good faith" effort to complete the remaining modifications, we have reassessed engineering and procurement status and have now determined that with the' exception of Item I.6, Pressurizer PORV, the modifications identified in our October 21, 1985 submittal will be
- completed this outage. Attachment 1 identifies the present status of the six items specified in our previous submittal. As noted in our previous submittal, the compensatory measures previously identified will remain in place until the modifications are completed.
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O 8511220162 851114 J0 PDR F
ADOCK 05000338 0\\\\
viEOin:A EE.ECTRIC AND POWER COMPANY TO Mr. Harold R. Denton The Pressurizer PORV modification may not be completed during this Unit i refueling outage because the position switch for the modification is not Category 1 seismically qualified.
Efforts are currently underway to qualify a switch by testing and engineering evaluation. This testing and engineering evaluation is scheduled to be completed by November 20, 1985.
If the switch can be successfully qualified in time to support the outage schedule, this modification will also be completed during the outage.
Presuming qualification cannot be completed in time to support the outage schedule, we are amending our schedular exemption request for the Pressurizer PORV to extend the completion date from the present 1985 refueling outage until the next refueling outage (currently scheduled to commence May 1, 1987). We will notify you of any subsequent changca in the status of the Pressurizer PORV modification.
If you have any questions or need additional information, please contact I
us.
Very truly yours, W. L. Stewart Attachment cc:
Dr. J. Nelson Grace Regional Administrator Region II Mr. T. E. Conlon NRC Region II Mr. M. Branch NRC Resident Inspector North Anna Power Station
Status Of Outstanding Appendix R Modifications Completion Item #
Title
- This Outage Status I.6 Pressurizer PORV Isolation No Category I (Seismic) switch was not available with the necessary number of contacts. Qualification testing and an engineering evaluation are being per-formed on a Category III switch. This testing and evaluation are scheduled to be complated by November 20, 1985. The modification will be installed if this switch is successfully qualified in time to support the outage schedule.
I.7 CVCS Normal Letdown Isolation Yes In Process.
I.8 CVCS Excess Letdown Isolation Yes In Process.
I.9 Reactor Vessel Head Vent and Yes In Process.
Pressurizer Vent Isolation I.10 Main Steam System Isolation Yes In Process.
s I.11 Steam Generator PORV Isolation Yes In Process.
- The following modifications are identified using the nomenclature used in Vepco's North Anna 10 CFR 50 Appendix R Report, Chapter 6.
A detailed description of each item is also available there.
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