ML043630277
| ML043630277 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/21/2004 |
| From: | Bauer S Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-05194-SAB/TNW/CJJ | |
| Download: ML043630277 (5) | |
Text
4.
iLWR Scott A. Bauer Department Leader Regulatory Affairs Palo Verde Nuclear Generating Station Tel: 623/393-5978 Fax: 6231393-5442 e-mail: sbauer~apsc.com 10 CFR 50.59 Mail Station 7636 P.O. Box 52034 Phoenix, AZ 85072-2034 102-05194-SAB/TNW/CJJ December 21, 2004 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, & 3 Docket Nos. STN 50-5281529/530 10 CFR 50.59 Report (January - December 2003)
Pursuant to 10 CFR 50.59(d)(2), Arizona Public Service Company is submitting the enclosed report. This report contains a brief description of each change and a brief summary of the evaluation required by 10 CFR 50.59(d)(1) for each change. This report contains all evaluations written during 2003, regardless of the implementation status of the evaluated action.
There were no NRC Commitment changes during 2003.
No commitments are being made to the NRC by this letter.
questions, please contact Thomas N. Weber at (623) 393-5764.
Should you have any Sincerely, SAB/TNW/CJJ/kg Enclosure cc:
B. S. Mallett M. B. Fields N. L. Salgado (all w/enclosure)
Li -7
ENCLOSURE PALO VERDE NUCLEAR GENERATING STATION ACRONYM/ABBREVIATION LIST AND 10 CFR 50.59 REPORT JANUARY - DECEMBER 2003
ACRONYMN/ABBREVIATION LIST AC Alternating Current AFW Auxiliary Feedwater System CENTS Combustion Engineering Nuclear Transient Simulation DMWO Design Modification Work Order GTGs Gas Turbine Generators MSIS Main Steam Isolation Signal OSG Original Steam Generator PROC Procedure PWSCC Primary Water Stress Corrosion Cracking RSG Replacement Steam Generator SG Steam Generator SGRP Steam Generator Replacement Project TMOD Temporary Modificaiton TS Technical Specifications TSP Tri-Sodium Phosphate
10 CFR 50.59 Annual Report (January - December 2003)
Log Doc Type E-03-00001 LDCR E-03-00002 LDCR E-03-00003 LDCR Doc Number 03-B003 03-F004 01 -F053 Description This revision to TS Bases 3.5.6 revised text describing surveillance test methods used to demonstrate the operability of Tri-Sodium Phosphate (TSP) bins installed for post-accident sump p1I control to reflect changes in the supporting analysis.
This revision to the UFSAR was the result of Revision 2 to Calculation 13-MC-ST-0016, which sizes the Tri-Sodium Phosphate (TSP) bins for post-accident sump pH control.
This revision to the UFSAR allows periodic load testing of GTGs to be performed while a Unit is in any plant mode. This is a change from information that was originally provided to the NRC describing the use of the GTGs as an Alternate AC source in compliance with 10 CFR 50.63, Station Blackout Rule. This change was initiated to allow APS to better manage plant risks in accordance with 10 CFR 50.65(a)(4), Maintenance Rule Summary This change does not require prior NRC approval in accordance with IOCFR50.59(c)(1).
This change does not require prior NRC approval in accordance with IOCFR50.59(c)(1).
This change does not require prior NRC approval in accordance with IOCFR50.59(c)(1).
E-03-00004 PROC 31 MT-9ZC07 This revision to procedure 3 IMT-9ZC07, Steam Generator Replacement Project Main Steam Pipe Spool Lifts allows the steam generator main steam pipe spools inside containment to be moved concurrently with movement of fuel between the reactor pressure vessel and the spent fuel pool. This 50.59 evaluated the use of a fault tree analysis to demonstrate the revised administrative controls during a specific heavy load movement is within the PVNGS original commitment to compliance with NUREG-0612.
This change does not require prior NRC approval in accordance with IOCFR50.59(c)(1).
E1-03-00005 DMWO 2513813 This modification to the pressurizer replaces a portion of each heater sleeve with new heater sleeve and weld material to mitigate the affects of PWSCC. This modification also replaces damaged heaters (like-for-like),
as required.
This change does not require prior NRC approval in accordance with IOCFR50.59(c)(1).
E-03-00006 PROC 40T1-9ZZ04 This procedure 40T1-9ZZ04, SGRP, AFW Waterhammer Flow Test is new. The objectives of the procedure arc to verify that the revamped auxiliary feedwater piping system and the replacement steam generator (RSG) feed ring are not damaged by full flow injection of auxiliary feedwater.
This change does not require prior NRC approval in accordance with IOCFR50.59(c)(1).
Page 1 of 2
Log Doc Type Doc Number Description Summary E-03-00009 DMWO E-03-O00010 LDCR E-03-00011I T-Mod 221240 03-F054 2659140 This modification to the Unit 2 SGs replaced OSG steam generator level transmitters and calibrated the new ones to the RSG requirements.
In addition, this includes a revision to the UFSAR to update response times for MSIS on high SG level in Mode 3 only.
This revision to the UFSAR reflects the new CENTS analysis for 3876 MWt and for the power uprate analysis completed for Unit 2.
This T-Mod provides an alarm in the Control Room to alert operators of declining pressure in the annulus space between the inner and outer o-ring seals of the Unit 2 reactor vessel.
This change does not require prior NRC approval in accordance with IOCFR50.59(c)(1).
This change does not require prior NRC approval in accordance with 10CFR50.59(c)(1).
This change does not require prior NRC approval in accordance with IOCFR50.59(c)(1).
Page 2 of 2