L-86-467, Forwards Oct 1986 Progress Summary of Select Sys Assessment
| ML20215C442 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/04/1986 |
| From: | Woody C FLORIDA POWER & LIGHT CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| L-86-467, NUDOCS 8612150141 | |
| Download: ML20215C442 (3) | |
Text
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P. O. BOX 14000, Juno BEACH, FL 33408
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- 00 e'oaio^ rowEn a ticwr coue4~v DECEMBER 04 1986 L-86-467-Dr., J. Nelson Grace Regional Administrator, Region 11 -
U. S. Nuclear Regulatory Commission 101 Marietta St., N.W., Suite 2900 Atlanta, GA 30323
Dear Dr. Grace:
Re: Turkey Point Onits 3 and 4 Docket Nos. 50-250 and 50-251 Select System Assessment Proaress Summary Attached please find the October 1986 progress ~ summary of the Select System
' Assessment.
. lf you have any questions regarding this information, please contact us.
Very truly yours, f ).
C.
. Woo Group V' e President Nuclear Energy COW /SAV/gp Attachment cc:
Harold F. Reis, Esq.
8612150141 861204 PDR ADOCK 05000250 R
PDR if I Z EC/
SAVl/009/l PEOPLE.. SERVING PEOPLE
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w WI FCT SYSTEM ASSESSMENT OCTOBER 1986 PROGRESS Reconstitution of Design Basis Development,' review and concurrence of the Chemical and Volume Control ~
System (Emergency Boration portion) draft reconsitituted : design - basis ' is proceeding on a schedule for issuance by February 1,1987.
Walkdowns Compilation, evoluotion and correction to walkdown discrepancies continues.
Walkdowns inside Unit 4 Containment have been completed. Walkdowns in areas of Units 3 and 4 occessible during Operation are in progress.
Configuration Monocement -
Evoluotion of procedures and other organizational responsibilities continues.
Punch List Significant items completed during this period by system, are listed below:
o Auxiliary Feedwater System
- Modified supports to chemical addition lines.
- Addressed increased stroke time of steam supply MOV.
o Emergency Filters
- Reviewed need to enter filters for performance testing.
o Emergency Containment Coolers
- None l
l o Emergency Power None o Containment isolation
- None i
l SAV1/009/2
_..,. ~. - _. _ - ~
M i
4:
- None
- Sandia Decay Heat Removal Report review.
o Main Steam isolation
- Reviewed vendor technical manuals for storage requirements.
o intake Coolina Water
- Closed NCRs on ICW structure thrust beams.
. - Closed NCR on 3A ICW pump cable conduit corrosion'.
- Closed NCR on corroded termination pull box.
- Closed NCR on corroded flex conduit.
l
- Closed NCRs on corroded termination lugs.
- Closed NCR on volve 50-3-407 rust.
- Addressed ficnge misalignment on basket strainer drain valve 326.
- Closed NCR on FE-1405 flange bolt thread engagement.
- Closed NCR on volve 50-3-403 corrosion.
- Closed NCR on "A" heat exchanger head flange bolt thread engagement.
- Closed NCR on TE-1464 conduit support welded to flange bolt head.
- Addressed concern that portions of U-3 ICW piping had insufficient support.
o' Component Coolina Water
= - None
- None o' Safety inlection System
- None o Vital Power r
- Color coded inverter fed instruments to match vital AC panels.
- Closed NCR on battery charger terminal block.
o Chemical and Volume Control
- None o Instrument Air
- None SAVI/009/3
-